20 EVENT FREQUENCY AND CROSS-COMPARISON ANALYSIS OF SEISMIC MONITORING SYSTEM FOR REACTOR TRIGA PUSPATI (RTP) Khairul Anwar Bapujee, Zareen Khan Abdul Jalil Khan, Mohd Khairulezwan Abdul Manan, Mohd Sabri Minhat, Nurfarhana Ayuni Joha, Muhammad Zulhelmi Mahadi and Mohamad Amirudin Mohamad Rosli ABSTRACT The Reactor Digital Instrumentation and Control System (ReDICS) plays a crucial role in monitoring and controlling Reactor TRIGA PUSPATI (RTP). It encompasses a seismic monitoring system that captures seismic information, including time history data and peak ground acceleration levels at the reactor building basement. This system features selfdiagnostic, testing capabilities and alerts plant operators following an event to assure continuous system and simplicity of operation and maintenance for Reactor TRIGA PUSPATI (RTP). The seismic monitoring system is capable of detecting and recording spike readings that exceed predetermined threshold levels andare savedas event data. Inthisstudy, the analysis of recorded event data used R Programming open source and it entails data preprocessing, event frequency and distribution analysis, and cross-comparison with historical seismic event records in peninsular Malaysia. Through statistical analysis of the data output, this study aims to assess and discuss the performance of the seismic monitoring system employed in Reactor TRIGA PUSPATI (RTP).
21 CENTRALIZED INTERFACE SYSTEM FOR LOW ENERGY ELECTRON ACCELERATOR (LEEA) Mukhlis Mokhtar, Dr. Leo Kwee Wah, Mohd Azhar bin Ahmad, Abd Halim bin Baijan, Rokiah binti Mohd Sabri, Mohd Faiz bin Mohd Zin, Puteri Nuraliah Husna binti Mohd Tajuddin, Mohd Noor Shafeek bin Jaafar and Mohammad Karimi bin Manawir ABSTRACT In Nuclear Malaysia, a localized own developed accelerator has started with Baby-EBM project in year 2002 with the initial energy of 140 keV [1] and then upgrade to Low Energy Electron Accelerator (LEEA) with initial energy of 250 keV. In the present status, this accelerator is undercommissioning status for upgrading the energy from 140 keV to 250 keV with the replacement of the high voltage power supply and development of the individual supporting systems such as scanning system, gas insulating system, window cooling system and etc. This replacement and upgrading subsystems need to be synchronize under one control system for an optimum energy output.
22 POSSIBILITY OF ELECTRON BEAM RADIATION CONVERSION TO X-RAY USING STAINLESS STEEL BY 3 MEV ELECTRON BEAM MACHINE FOR FOOD IRRADIATION APPLICATION Ruzalina Baharin, Ahmad Zainuri Dzomir, Hasan Sham, Shalina Sheik Muhammad, Siti Zulaiha Hairaldin, Harzawardi Hasim, Azmi Ali, Mohamad Hakiman Mohamad Yusoff, Mohamad Zulhailmee Mohd Zainal, Muhd Izham Ahmad, Mohd Suhaimi Jusoh, Shahrina Akma Mansur, Noor Hasni M. Ali and Ros Anita Ahmad Ramli ABSTRACT Food irradiation in Malaysia has been started since the 1980s and is slowly gaining acceptance from the industry. The Malaysian Nuclear Agency (Nuklear Malaysia) as a research institute plays a major role in introducing and conveying the benefits of food irradiation to people. A number of researches have been done to show the benefits of food irradiation. To support these activities, MINTec-Sinagama, a gamma irradiation facility with a Cobalt-60 radioactive source, has been established by the Malaysian government at Nuclear Malaysia, Bangi. The main activity is to irradiate herbs, spices, seasoning and dried food at early operation. Since then, the types of products have been increasing with the demand from the industry until now. In addition to Cobalt-60, electron beam (EB) machine accelerator voltage (up to 10 MeV) and X- ray machine (up to 7.5 MeV) are also allowed to be used in food irradiation. WHO, USDA and IAEA have established rules and procedures for food irradiation. Malaysia adapted the regulations and created the Food Irradiation Regulations 2011 embedded in the Food Act 1983 under the jurisdiction of the Ministry of Health (MOH), Malaysia. With this motivation, Nuclear Malaysia is exploring the possibility of converting the EB radiation from the medium range 3 MeV EB machine,
23 EPS3000 to X-ray. Nuclear Malaysia has EB irradiation facility, ALURTRON, mainly irradiating cables and wires for crosslinking and silicon wafer semiconductors to improve electronic properties. EPS3000 has low penetration compared to gamma rays with a maximum depth of 1.5 cm product packaging at normal density. Therefore, no food irradiation can be done using the EPS3000 EB machine due to the large product packaging. In this paper, we describe the work done with a stainless-steel beam shutter as a possible converter from electron beam to X-ray. It is located under the scanner horn and will be pulled to the side when irradiating the product. The beam shutter has a water channel to stop unwanted electrons coming from the bremsstrahlung radiation. In the previous work done by ALURTRON in 2004, the measured dose can be seen in encouraging data. This work was also contributed by the expert through IAEA/RCA project activities RAS5087.
24 RADIONUCLIDES CONCENTRATION IN POTATO CRISPS, THE EFFECTIVE DOSE AND ASSOCIATED CANCER RISK TO MALAYSIAN ADULTS Yii Mei-Wo, Dainee Nor Fardzila Ahmad Tugi, Maziah Mahmud, Nor Aza Hassan and Mohd Asri Ramli ABSTRACT Consumption of foods containing radionuclides may contribute to radiation dose and poses higher cancer risk to human. Studies were conducted to determine concentration of radionuclides present in commercial potato crisps. Based on the consumption rate by Malaysian adults, annual effective dose value and the associated cancer risk were estimated. The activity concentration was found ranged in between 181 to 395 Bq/kg for the natural 40K. Meanwhile for the other natural radionuclides of 226Ra, 228Ra, 232Th, 238U, it was ranged between 1.01 – 6.72 Bq/kg, 0.92 – 4.90 Bq/kg, 0.69 –3.46 Bq/kg and 1.81 –12.60 Bq/kg, respectively, whilst the artificial radionuclides were less than 1 Bq/kg. Calculated annual effective doses due to this intake of radionuclides by ingestion was estimated in between 28.7 – 88.9 μSv/y, with potential of cancer risk incurrence between 10 to 31 cases in every 100,000 people. Keywords: Radionuclides, potato crisps, effective dose, cancer risk ABSTRAK Pengambilan makanan yang mengandungi radionuklid boleh menyumbang kepada dos sinaran dan menimbulkan risiko kanser yang lebih tinggi kepada manusia. Kajian telah dilakukan untuk menentukan kepekatan radionuklid yang terkandung dalam kerepek kentang komersil. Berdasarkan kadar pengambilan kerepek oleh rakyat dewasa Malaysia, nilai dos berkesan tahunan dan risiko kanser yang berkaitan telah dikirakan. Kepekatan keaktifan didapati berada di antara 181 hingga 395 Bq/kg untuk 40K tabii. Manakala untuk radionuklid
25 semulajadi yang lain, 226Ra, 228Ra, 232Th, 238U, ia adalah masingmasing berjulat antara 1.01 – 6.72 Bq/kg, 0.92 – 4.90 Bq/kg, 0.69 – 3.46 Bq/kg and 1.81 –12.60 Bq/kg, sementara radionuklid buatan adalah kurang dari 1 Bq/kg. Pengiraan dos berkesan tahunan akibat pengambilan radionuklid melalui permakanan tersebut didapati antara 28.7 – 88.9 μSv/t, dengan potensi kejadian risiko kanser sebanyak 10 hingga 31 kes dalam setiap 100,000 orang. Kata kunci: Radionuklid, kerepek kentang, dos berkesan, risiko kanser
26 BOREHOLE DISPOSAL FACILITY FOR DISUSED SEALED RADIOACTIVE SOURCES (DSRS) CONSTRUCTION PHASE STATUS Nazran bin Harun, Mohd Zaidi bin Ibrahim, Dr. Azmi bin Ibrahim and Nurul Syazwani binti Yahaya ABSTRACT The borehole disposal facility is part of Nuklear Malaysia's effort to ensure that its disposal activity is conducted in a manner that will protect and maintain environmental quality. The construction phase is physically estimated to commence in a month from 30th May 2023. Updating activity records are necessary documents in compliance with requirements imposed by the Department of Atomic Energy Malaysia for Class G license. The update status is set out to record construction activities comprising drilling, constructing and sealing of a disposal borehole for disused sealed radioactive sources (DSRS) in Malaysia following the specific requirements outlined by the International Atomic Energy Agency (IAEA) and Department of Atomic Energy Malaysia, in the optimum time, in the most viable and safe manner to the satisfaction of all parties involved. After the construction phase is completed, the disposal phase will take place starting with provisional and cold testing IAEA expert mission before waste emplacement is conducted on the borehole disposal facility. Keywords: borehole, disposal, DSRS, construction
27 EVALUATION OF RELATIONSHIP MODEL FOR GAP AND OVERLAP RATIO WITH DOSE RATE IN THE DESIGN OF BUNKERS LEAD DOOR Mohd Zaid bin Hassan@Abdul Rahman, Muhammad Hannan bin Bahrin, Mohd Rizal bin Mamat @ Ibrahim, Azraf bin Azman, Anwar bin Abdul Rahman and Syed Asraf Fahlawi Wafa bin S M Ghazi ABSTRACT This paper presents the process evaluation of the relationship model between the gap and overlap in the design of the bunker lead door. The reference model was successfully developed using Particle and Heavy Ion Transport code System (PHITS) simulation software. This study is to prove the accuracy of the relationship model with an optimised correction factor. The introduction to the optimum relationship model is a cost and time-saving approach for determining the permissible ratio of gap and overlap in radiation facility design. Keywords: Attenuation, bunker, lead door, gap, overlap, PHITS ABSTRAK Kertas kerja ini menerangkan tentang proses penilaian model hubung kait bagi nilai celahan dan pertindihan dalam reka bentuk pintu plumbum untuk bilik dedahan. Model rujukan telah dibuat menggunakan perisian simulasi PHITS. Kajian ini adalah untuk membuktikan ketepatan model hubung kait yang telah dibangunkan dengan faktor pembetulan yang optimum. Penghasilan model hubung kait yang optimum merupakan pendekatan penjimatan kos dan masa dalam menentukan nilai celahan dan pertindihan dalam reka bentuk bilik dedahan.
28 EVALUATION OF LEAD EQUIVALENT THICKNESS OF X-RAY ROOMS IN HEALTH CLINICS IN KELANTAN STATE Azuhar Ripin, Mohd Khalid Matori, Shahrul Azlan Azizan, Mohd Muzammil Abd Jalil, Md Khairusalih Md Zin, Mohamad Al Rasyidin Mohamed Najib and Muhammad Yusri Yahya ABSTRACT Lead equivalent thickness (LET) is a technique used to evaluate the shielding capability of shielding materials constructed for X-ray rooms. Assessment of shielding thickness based on LET was carried out in ten government health clinics in the state of Kelantan in collaboration with the State Health Department (JKN). This measurement used an Am-241 radiation source and a Raysafe 452 radiation detector for the entire test run. Thistest hasmeasuredallfour-radiation roomwalls, lead doors, lead glass, all lead doors and lead glass frames, switches, sockets and weak points found in the X-ray room. Based on the results obtained, all walls, leaded glass and leaded doors meet the minimum standard requirements of the Ministry of Health Malaysia (MOH). However, there is significant radiation leakage in the lead doorframe, lead glass frame and door gap. The clinic has been advised to repair and upgrade the detected leaks before being used. Therefore, LET is a crucial measurement that needs to be carried out to ensure that the thickness of materials and rooms constructed for radiation facilities are sufficient to protect patients, staff and the public from the harmful effects of ionizing radiation. Keywords: Lead equivalent thickness (LET), X-ray, Raysafe 452, Health clinics
29 ABSTRAK Ketebalan kesetaraan plumbum (LET) adalah teknik yang digunakan untuk menilai keupayaan pemerisaian bahan perisai yang digunakan untuk membina bilik sinar-X. Penilaian ketebalan perisai berasaskan LET telah dilaksanakan di sepuluh klinik kesihatan kerajaan di negeri Kelantan dengan kerjasama Jabatan Kesihatan Negeri (JKN). Pengukuran ini telah menggunakan punca sinaran Am- 241 dan pengesan sinaran Raysafe 452 untuk keseluruhan ujian yang dijalankan. Ujian ini telah mengukur keempat-empat dinding bilik sinaran, pintu plumbum, kaca plumbum, kesemua pintu plumbum dan bingkai kaca plumbum, suis, soket serta titik-titik lemah yang terdapat di dalam bilik sinar-X. Berdasarkan kepada keputusan yang diperolehi, kesemua dinding, kaca plumbum dan pintu plumbum adalah memenuhi keperluan piawaian minimum Kementerian Kesihatan Malaysia (KKM). Walau bagaimanapun, terdapat kebocoran sinaran ketara pada bingkai pintu plumbum, bingkai kaca plumbum dan selisih pintu. Pihak klinik telah disarankan untuk membaiki dan menaik taraf kebocoran yang dikesan sebelum digunakan. Oleh itu, LET merupakan pengukuran yang penting yang perlu dijalankan bagi memastikan bahawa ketebalan bahan dan bilik yang dibangunkan untuk kemudahan sinaran adalah mencukupi bagi melindungi pesakit, kakitangan dan orang awam daripada kesan berbahaya sinaran mengion Kata kunci: kesetaraan plumbum, sinar-X, Raysafe 452, Klinik Kesihatan Kerajaan
30 PEMANTAUAN SINARAN DI MAKMAL KIMIA ANALISIS AGENSI NUKLEAR MALAYSIA Md Derus bin Ibrahim, Noor Fadilla binti Ismail, Syerin Aidora binti Salim dan Mohd Khushairi Awang ABSTRAK Pemantauan sinaran di Makmal Analisis Kimia (ACA) adalah sangat penting kerana di makmal tersebut terdapat sampel-sampel yang telah diradiasi melalui beberapa teknik seperti daripada kaedah rak berputar (RR) atau system penghantaran pneumatik (PTS). Kakitangan yang bertugas di kawasan tersebut juga mudah untuk terdedah kepada kontaminasi radioaktif. Dos pekerja sinaran turut direkodkan dari tahun 2020 sehingga tahun 2023. Kesemua dos individu yang berkerja di Makmal ACA adalah rendah dan selamat. Dos Kawasan di Makmal ACA juga dipantau dari masa ke semasa. Kata kunci: Pemantauan Sinaran, Pekerja Sinaran, Reaktor Triga Puspati, Rak Berputar (RR), Sistem Penghantaran Pneumatik (PTS) dan Analisa Pengaktifan Neutron (NAA) ABSTRACT Radiation monitoring at the Chemical Laboratory Analysis is important because here, samples from the field are irradiated through the Rotary Rack (RR) or Pneumatic Transfer System (PTS), method using neutrons from the Puspati Triga Reactor facility. Radiation workers will be exposed to radiation or contamination of radioactive materials when samples of Rotary Rack (RR) or Pneumatic Transfer System (PTS) samples are taken and measured in the laboratory for Neutron Activation Analysis (NAA)
31 RADIATION SHIELDING FOR CWT 3 MeV 30mA ELECTRON BEAM ACCELERATOR BUNKER Muhamad Zahidee Taat, Noor Fadilla Ismail and Mohd Izham Ahmad ABSTRACT This paper addresses the designated of radiation shielding bunker for 3MeV 30mA electron beam accelerator that was installed at Cyprium Wire Technology Sdn. Bhd. (CWT). The bunker was designed by CGN Dasheng Electron Accelerator Technology Company (CGN). The verification focus on the wall thickness at the surrounding bunker at ground floor, the wall thickness at 1st floor of the building and also the rooftop. The primary design for this facility is for wire and cable crosslinking processing. Malaysian Nuclear Agency has been appointed to monitor, verify and advise CWT in order to ensure the designated shielding bunker is safe and fulfilled all the requirements set up by the regulatory body. This verification will be conducted using a calculation as recommended by NCRP 51.
32 LEAD EQUIVALENT TEST FOR SYRINGE CONTAINERS USING IN NUCLEAR MEDICINE Norriza binti Mohd Isa, Azuhar bin Ripin, Mohd Khalid bin Matori, Mohamad Al Rasyidin bin Mohamed Najib, Nur Shahriza binti Zainuddin, Md Khairusalih bin Md Zin and Asmahani binti Ibrahim ABSTRACT Lead syringe shield is almost used in Nuclear Medicine to protect ionising radiation worker from secondary radiation. However, it have to undergo integrity test for guaranty the radiation safety before using for medical use. The aim of the study is to determine of lead equivalent thickness (LET) for four new samples of syringe container shield from a local manufacturer. In the study, a the results from commercial syringe was compared with the samples results. The LET is evaluated at five parts at the syringe containers by utilizing calibration curve which was built up with Co-57 radiation source and 14 lead sheets with thickness was 0.1 mm per sheet. The collimated beam from the source were detected by using a radiation detector. Scattered radiation test was also carried out at 100 cm as Source Detector Distance (SDD) in the study. All the data from the study were collected and analysed. The result shown much larger discrepancies of LET between the samples and commercial syringe container. Meanwhile the LET results among the samples were not represent obvious different each others. Only the top layer of sample's containers are good agreement with user requirement, but the rest parts are disagreed. Keywords: Syringe Container Shield, Lead Equivalent Thickness, Radiation Protection, Radiation Worker, Nuclear Medicine
33 ABSTRAK Perisai picagari plumbum banyak digunakan dalam perubatan nuklear untuk melindungi sinaran mengion sekunder kepada pekerja sinaran. Walau bagaimanapun perisai ini perlu menjalani ujian integrity untuk menjamin keselamatan sinaran sebelum digunakan untuk kemudahan perubatan. Tujuan kajian ini untuk menentukan ketebalan kesetaraan plumbum (LET) untuk empat sampel baru bekas picagari berperisai daripada sebuah syarikat pembuat tempatan. Dalam kajian ini, satu bekas picagari yang sediada di pasaran digunakan dalam ujian ini di mana keputusannya yang diperolehi akan digunakan untuk tujuan perbandingan dengan keputusan ujian dari sampel yang diuji. LET dinilai pada 5 bahagian pada setiap bekas picagari dengan menggunakan graf kalibrasi yang dibangunkan dengan menggunakan sumber sinaran Co-57 dan 14 lapisan plumbum yang ketebalan setiap satunya adalah 0.1 mm. Alur sinaran yang dikolimat dari sumber sinaran dikesan menggunakan satu pengesan sinaran. Ujian sinaran serakan turut dijalankan dalam kajian ini pada jarak sumber dan pengesan (SDD) adalad 100 cm. Kesemua data kajian dikumpul dan dianalisa. Keputusan LET menunjukkan perbezaan ketara antara bekas sampel picagari dengan bekas picagari yang tersedia di pasaran pada semua bahagian bekas yang diuji. Manakala keputusan LET antara bekas-bekas sampel tidak menunjukkan perbezaan ketara pada semua bahagian ujian. Hanya lapisan atas bagi semua bekas sampel yang memenuhi keperluan pengguna di hospital tetapi tidak pada bahagian lain sampel-sampel yang diuji.
34 HAND-HELD LASER SAFETY: MORE THAN MEETS THE EYE Shamesh Raj Parthasarathy, Amierah Hazimah Mohd Hashim, Zulkifli Yusof and Muhammad Khairul Amir Hamid ABSTRACT Hand-held Laser consists of variety of colours with different wavelength. The most common ones come in blue with wavelength of 405 nm, green with a wavelength of 532 nm and red with wavelength of 650 nm. Lasers have many benefits in human’s lives, however, it can also bring major threat if it is not used wisely. This is because, high-powered lasers may damage our skin and eyes. With just a click of a button, it can either be helpful for human’s lives or it can be a threat to human’s health. Lasers are not only used by adult, but it can be easily accessed by children which posed more threat because children only see those lasers as toys. Human eye can transmit and focus on light with range wavelengths of 400 to 1400 nm with an optical concentration power of approximately 100,000. In the visible spectrum (400-700nm), the human aversion response to bright visible light can generally be relied upon to protect against potential injury from Class 3R laser with power limit 5mW. However, the aversion response cannot be relied upon for near- infrared (IR) wavelengths (700-1400nm) where the human eye is less sensitive. In this study, the hazard levels of the Hand-held Lasers were determined according to the ANSI Z136.1 and IEC 60825.1 standard. The objective of this study is to first and foremost, determine the wavelength and power of the stated Lasers and compare with the one labelled in the respective label. From the output power measured, the irradiance of each Handheld Lasers was calculated and compared with the MPE. Finally, a laser hazard evaluation was performed.
35 HARI KEDUA KATEGORI PEMBENTANGAN LISAN
36 TRANSFORMASI PERHUBUNGAN E-MEL DI AGENSI NUKLEAR MALAYSIA KE MYGOVUC 2.0 Saa'idi bin Ismail, Mohamad Safuan bin Sulaiman, Mohd Dzul Aiman bin Aslan, Siti Nurbahyah binti Hamdan dan Norzalina binti Nasirudin ABSTRACT Email communication continues to play a crucial role in facilitating efficient and secure communication exchange within an organization. This paper presents a technical and critical observational study encompassing technical requirements, stakeholder involvement, data migration, challenges, and technological changes in Malaysian Nuclear Agency. The paper also discusses the expected outcomes and benefits to be achieved through these changes. The MyGovUC platform was initially introduced as a unified communication solution for government agencies in Malaysia to enhance collaboration, and MyGovUC 2.0 improves government service delivery while achieving cost savings. Keywords: efficient and secure information exchange, technological change challenges, unified communication.
37 DIGITALIZATION OF MARINE RADIOACTIVITY DATA IN MALAYSIA Mohamad Safuan Sulaiman, Noor Fadzilah Binti Yusof, Nurfatini Abd Ghani, Siti Nurbahyah binti Hamdan, Yii Mei Wo, Jalal bin Sharib@Sarip, Norfaizal bin Mohamed@Muhammad ABSTRACT Marine radioactivity data in Malaysia were acquired many years ago. It began with manual recording process using paper, pen, and pencil. Since year 2003, it has been consistently recorded and stored in MS Excel sheet. As time went by, the marine radioactivity data need to be accessible online and widely used for regional and international collaborations. For example, the data is shared at the international level such as the Global Marine Radioactivity Database (GLOMARD) [1] organized by the IAEA Marine Environment Laboratory (MEL). The sharing of the data [2]is important because it has been used as a basis for radiation dose assessment, provision oftemporal trends and levels as well as finding the information gap at national, regional, and international levels. In Malaysia perspective, data in MS Excel sheet couldonly be accessedbyRadiochemistry and Environmental Laboratory (RAS) [3] personnel, and not widely available for scientific research and investigation (except the published data). It is also less structured, scattered and conducted with less systematic way. Due to those conditions, presentation and validation of the data could be argued and may not comply with the requirement of radiological assessment standard of practice. Therefore, development of an appropriate radioactivity database system that considering data from various matrices such as sediment, water, biota and plankton in sea and freshwater environment is proposed
38 DEVELOPMENT OF NUKLEAR MALAYSIA SOURCE CODE REPOSITORY SYSTEM FOR SECURITY REVIEW AND BACKUP Mohd Dzul Aiman bin Aslan, Saa'idi bin Ismail, Siti Nurbahyah binti Hamdan, Mohamad Safuan bin Sulaiman, Maizura binti Ibrahim, Nur Fatini binti Abd Ghani and Nursuliza binti Samsudin ABSTRACT In the contemporary era, the development of systems is now open to any company, organization, or individual. These developed systems serve to streamline the daily tasks of organizations. For organizations like Nuklear Malaysia, the emphasis on system development is currently not only centered around system effectiveness but also includes a keen focus on issues related to security and source code integrity. Within Nuklear Malaysia, there are more than 30 systems that have been developed in-house as well as using external resources. This paper presents the development of the Nuklear Malaysia Source Code Repository System (NMSRS) utilizing GitLab as a platform to enhance the security aspects of system development. NMSRS aims to provide a robust and trusted solution for reviewing and securely storing Nuklear Malaysia's source code, safeguarding intellectual property and sensitive information. Additionally, this paper elaborates on the design and implementation aspects of NMSRS, including key features such as code versioning, access control, issue tracking, and continuous integration/continuous deployment (CI/CD) capabilities, alongside code reviews for security concerns. Keywords: Source Code, Security, Cybersecurity, Application Development
39 PEMBANGUNAN API DENGAN MENGGUNAKAN LARAVEL (API DEVELOPMENT USING LARAVEL) Nur Fatini binti Abd Ghani, Nursuliza binti Samsudin, Siti Nurbahyah binti Hamdan, Maizura binti Ibrahim, Mohd Dzul Aiman bin Aslan, Mohamad Safuan bin Sulaiman, Saa'idi bin Ismail, Mohd Hasnor bin Hasan, Sufian Norazam bin Mohamed Aris dan Radhiah binti Jamalludin ABSTRAK Di Nuklear Malaysia, terdapat permintaan yang semakin meningkat terhadap projek-projek [1] seperti pembangunan pangkalan data, aplikasi mudah alih, projek Internet of Things (IoT), teknologi automasi, Kecerdasan Buatan (Artificial Intelligence, AI) serta pengembangan aplikasi untuk berbagai keperluan Permintaan terknologi yang berkembang ini memerlukan platform pelbagai disiplin yang dapat menampung permintaan teknologi baharu dan pelbagai. Walaubagaimanapun menjadi cabaran kepada Agensi menangani isu yang dihadapi oleh sistem web konvensional semasa yang sukar diubah suai untuk memenuhi keperluan tersebut. Di sinilah peranan API dimainkan – API berfungsi sebagai jambatan yang menghubungkan platform web konvensional agensi dengan kemunculan teknologi baharu akan datang. Menyedari keperluan untuk memodenkan web konvensional organisasi kepada infrastruktur yang lebih dinamik, kertas kerja ini akan menumpukan usaha untuk membangunkan RESTful (Representational State Transfer) API. RESTful API memperkenalkan set spesifikasi teknikal dan garis panduan untuk membuat perkhidmatan web menggunakan protocol HTTP untuk bertukar sumber web dalam Format JSON (JavaScript Object Notation) [5] . Kaedah ini dapat meningkatkan kebolehbacaan data dan integrasi yang lebih cekap antara pelbagai platform. Pada masa ini, banyak perkhidmatan web telah dibangunkan
40 menggunakan seni bina REST [2] kerana reka bentuk REST menawarkan keupayaannya untuk menghantar permintaan dan menerima respons dengan cara yang jelas dan standard [3] supaya dapat difahami oleh kebanyakan teknologi baharu. Syarikat besar seperti Twitter[13] , Amazon [14] dan Facebook [15] juga telah melaksanakan antara muka REST kepada pembangunan aplikasi di luar sistem mereka kerana kerana REST menawarkan penggunaan bahasa atau platform pengaturcaraan yang berbeza [4] . Dengan memanfaatkan arkitektur REST, kertas kerja ini akan membincangkan pembangunan API menggunakan Laravel sebagai rangka kerja dan pelaksaanan Jason Web Token (JWT) sebagai kaedah pengesahan yang selamat. Gabungan ini dipercayai dapat mencipta antara muka yang berstuktur dan selamat untuk pertukaran data dan interaksi antara aplikasi yang berbeza [6] [7] [8] [9] [10] . Bagi menilai RSTful API yang dibangunkan kertas kerja ini akan menggunakan perisian Postman.
41 PEMBANGUNAN MODUL DALAM SISTEM SHAREPOINT SECARA INTRANET DI AGENSI NUKLEAR MALAYSIA Radhiah binti Jamalludin, Siti Nurbahyah binti Hamdan, Mohamad Safuan bin Sulaiman, Mohd Dzul Aiman bin Aslan, Raja Murzaferi Raja Moktar, Norzalina binti Nasirudin, Khairiel Adyani bin Abd. Ghani dan Shahrizan bin Saharudin ABSTRAK SharePoint merupakan satu platform kolaborasi dan pengurusan maklumat yang membolehkan perkongsian maklumat, penyimpanan dokumen, dan pengurusan tugas secara terpusat. Pelbagai modul yang telah dibangunkan di dalam sistem ini yang dapat membantu pengguna mendapatkan data dari kalangan warga Nuklear Malaysia. Disamping itu, ia adalah pemudahcara kepada para penyelidik dalam membuat perkongsian penyelidikan yang telah dibuat agar maklumat dapat disampaikan dengan cara yang berkesan tanpa menghadapi risiko kesalahan manusia dengan pemantauan secara atas talian. Sistem ini dilengkapi dengan fitur keselamatan SSL dan ianya boleh dicapai pada bila-bila masa dan dimana-mana sahaja. Kertas kerja ini akan menerangkan modul- modul fungsian saintifik yang diperlukan oleh bahagian atau unit bagi mendapatkan data bagi tujuan tertentu. Pihak Pusat Teknologi Maklumat (PTM) menyediakan khidmat nasihat kepada pengguna bagi membangunkan modul yang diinginkan dengan ketersediaan infrastruktur yang sedia ada. Terdapat kekangan peruntukan dalam menaiktaraf sistem SharePoint untuk mengikuti peredaran teknologi semasa agar lebih mesra pengguna dan dapat dinikmati oleh semua warga Nuklear Malaysia. Kata kunci: platform kolaborasi, pengurusan maklumat secara terpusat, pemantauan secara atas talian, keselamatan capaian
42 THE COMPUTERIZED AUTOMATION OF THE NUCLEAR/RADIOACTIVE MATERIALS ACCOUNTING SYSTEM (CARMA SYSTEM) BASED ON THE PUBLIC SECTOR APPLICATION SYSTEM ENGINEERING GUIDE BOOK (KRISA) Maizura binti Ibrahim, Siti Nurbahyah binti Hamdan, Amy Hamijah binti Ab Hamid, Mohd Hasnor bin Hasan, Mohd Dzul Aiman bin Aslan, Nur Fatini binti Abd Ghani, Nursuliza binti Samsudin and Mohamad Safuan bin Sulaiman ABSTRACT A number of security systems, either 'a manual security system' or 'a computer-based security system' are established in the Malaysian Nuclear Agency (Nuklear Malaysia) to provide protection for nuclear/radioactive materials, associated facilities, and associated activities. A manual security system is defined as a human-managed nuclear security system without any automated computer- aided system such as the existing inventory of radioactive materials recorded in the inventory log book, utilizing the Microsoft Excel application, or Inventory Cards to record, perform, and monitor the Nuclear/Radioactive Material Accounting (NRMAC) related activities. Manual-based systems need human intervention in every step of the procedure, such as updating the inventory card and log book, hence performing the calculation ofthe inventory to produce the balance sheet of the NRMAC. This kind of system is highly exposed to error-prone made by human careless and neglecting behavior. Apart from that, it lacks benefits in terms of aiding situational awareness of the securityof nuclear/radioactive materials because no automated alert could be generated if an imbalance in inventory happens. Therefore, this paper presented a conceptual design of a new web-based application system called the Computerized Automation of the Nuclear/Radioactive Materials Accounting System (CARMA System). The CARMA system is proposed to be developed to automate the process and computerized
43 the process of record keeping and inventory of nuclear/radioactive materials. This system is one of the base components in the Integrated &Intelligent Nuclear Security System (I2NS), aimed to fulfill the scope of improving security measures in controlling and monitoring the outsiders and the insiders dealing with radioactive materials. The conceptual design is developed following the Public Sector Application System Engineering Guide Book (Buku Panduan Kejuruteraan Sistem Aplikasi Sektor Awam, KRISA) published by MAMPU. ABSTRAK Di Agensi Nuklear Malaysia (Nuklear Malaysia) telah diwujudkan beberapa sistem keselamatan, sama ada 'sistem keselamatan yang manual' atau 'sistem keselamatan berasaskan komputer' sebagai langkah untuk melindungi sekuriti bahan nuklear/radioaktif, kemudahan berkaitan dan aktiviti yang berkaitan. Sistem keselamatan manual ditakrifkan sebagai sistem sekuriti nuklear yang diuruskan sepenuhnya oleh manusia tanpa sebarang bantuan sistem berasaskan komputer seperti sistem inventori sedia ada untuk bahan radioaktif, yang mana, ianya direkodkan di dalam buku log inventori, menggunakan aplikasi Microsoft Excel, atau Kad Inventori. Ianya bertujuan untuk merekod, melaksana, dan memantau aktiviti berkaitan Perakaunan Bahan Nuklear/Radioaktif (NRMAC). Sistem manual memerlukan campur tangan manusia dalam setiap langkah prosedurnya, seperti mengemaskini kad inventori dan buku log, seterusnya melaksanakan pengiraan inventori untuk menghasilkan kunci kira-kira NRMAC. Sistem seperti ini sangat terdedah kepada ralat yang disebabkan oleh tingkah laku manusia yang cuai dan sifat yang mengabaikan. Selain itu, sistem yang dilaksanakan secara manual tidak berupaya membantu dari segi meningkatkan kesedaran situasi tentang sekuriti bahan nuklear/radioaktif kerana tiada amaran automatik boleh dijana sekiranya ketidakseimbangan dalam inventori berlaku. Oleh itu, kertas kerja ini membentangkan rekabentuk konsep sistem aplikasi berasaskan
44 web baharu yang dinamakan Sistem Automasi Berkomputer Perakaunan Bahan Nuklear/Radioaktif (Sistem CARMA). Sistem CARMA dicadangkan untuk dibangunkan bagi mendigitalkan serta mengautomasikan proses penyimpanan rekod dan inventori bahan nuklear/radioaktif, yang mana pada masa kini ianya dilaksanakan secara manual. Sistem ini merupakan salah satu komponen asas di dalam Sistem Sekuriti Nuklear Bersepadu dan Pintar (I2NS). Ianya bertujuan untuk memenuhi skop penambahbaikan langkah keselamatan dalam mengawal perakaunan bahan radioaktif dan memantau pihak luar dan orang dalam yang berurusan dengan bahan nuklear/radioaktif. Reka bentuk konsep yang dibentangkan di dalam kertas kerja ini dibangunkan berdasarkan Buku Panduan Kejuruteraan Sistem Aplikasi Sektor Awam (KRISA) yang dikeluarkan oleh MAMPU.
45 EFFECT OF ULTRAVIOLET IRRADIATION DOSE ON MECHANICAL PROPERTIES OF HYBRID ULTRAVIOLET PEROXIDE PREVULCANIZED NATURAL RUBBER LATEX Sofian Ibrahim, Chai Chee Keong, Muhammad Hannan Bahrin, Hasan Sham, Mohd Noorwadi Mat Lazim, Anwar Abdul Rahman, Ahmad Bazlie Abdul Kadir, Noor Mohd Rizwan Brahim, Khairul Hisyam Mohamed Yusop, Hafizuddin Maseri, Siti Hajar Said, Wan Ismail Wan Yusof, Muhamad Nor Atan and Noor Hasni M Ali ABSTRACT At present, there are three main vulcanization procedures being used in rubber latex industries; which is sulphur, radiation and peroxide vulcanization. However, another vulcanization technique that began to receive serious attention from researchers is UV vulcanization. This paper will discuss the effect of UV irradiation time and dose on the mechanical properties of hybrid UV and peroxidation vulcanizations. Latex compounding formulations are developed based on 2.0 parts per hundred rubber (phr) of 2 –hydroxyl-2-methyl-1-phenylpropanone (Irgacure 1173) as the photoinitiator, 0.5 phr of tertbutyl hydroperoxide (tBHPO) as the sensitizer, 2.0 parts per hundred rubber (phr) of hexanediol diacrylate (HDDA) as the co-sensitizer and 0.5 phr of hydroxyacetone (Hac) as the activator. The formulated latex was exposed to UV irradiation at 0, 15, 30, 45 and 60 minutes using a 4x55 watt germicidal lamp. The rubber film obtained from UV irradiation at 30 minutes or 6674.22 mJ/cm2 radiation dose had tensile strength, modulus @ 500% and modulus @ 700 % of 25.1, 2.3 and 8.0 mPa respectively, which is more than 400 % increment compared to control film. Besides, the crosslink percentage of the rubber film was recorded at 93 %. Keywords: vulcanization, UV radiation, latex
46 PREPARATION AND CHARACTERIZATION OF POLYVINYL CHLORIDE (PVC)/IRRADIATED POLYTETRAFLUOROETHYLENE (i-PTFE) COMPOSITE VIA IN-SITU POLYMERIZATION Noora’tiqah Mohamad Fauzi, Sarala Selambakkannu, Norshafarina Ismail, Ting Teo Ming, Mohd Shahrulnizam Ahmad, Farah Fadzehah Hilmi and Muhammad Aidell Amir ABSTRACT Polymers have been well-known for their versatility which enables them to be used widely in advanced applications. Typically, high-performance polymers used in sophisticated technologies require distinctive characteristics such as enhanced mechanical strength, durability, flexibility, and resistance to degradation (Hsissou et al., 2021). However, essentially a single polymer is unlikely to meet the requirements for commercially significant polymers for advanced applications. Thus, the development of polymer composites attracted global attention. Polymer composites are composed primarily of reinforcement and matrix. As a matrix and reinforcement, the composite may contain metals, ceramics, and other polymers as well (Nawab, Sapuan, & Shaker, 2021). Furthermore, thermosetting and thermoplastic resins are widely used as matrix materials in polymer composites. Thermo-sets are low in viscosity, while thermoplastics are recyclable. The most common polymeric matrices used in composites are polypropylene (PE), polyethylene (PP), acrylonitrile butadiene styrene (ABS), and polyvinyl chloride (PVC). PVC used widely in industrial, technical, and daily applications, including building, transport, packaging, electrical/electronic, and healthcare sectors. Moreover, PVC is often combined with other substances such as metals, salts, and nanoparticles to improve its toughness and impact properties (Lewandowski & Skórczewska, 2022). Nevertheless, one of the major disadvantages of PVC is its low heat distortion temperature, which limits its applications across multiple disciplines (Shi, Zhang, &
47 Zhao, 2012). However, blending PVC with other polymers significantly increases the heat distortion temperature of the latter. In this study, i-PTFE blended with PVC in order to improve the thermal properties. Previously, it is reported that silicone rubber composites with excellent mechanical properties, little temperature-dependent friction change, and exceptional high-temperature abrasion resistance were produced with the addition of PTFE and the use of fluoro-silicone rubber as a compatibilizers (Qi et al., 2020). Prior to polymerization with PVC, PTFE was irradiated with cobalt-60. The purpose of PTFE went through irradiation is to reduce its molecular weight, which improves interfacial bonding with PVC during polymerization (Lunkwitz, Lappan, & Lehmann, 2000). Therefore, this study aims to determine the optimal conditions and parameters for in-situ polymerization, including a thorough exploration of i-PTFE compositions. In addition, comprehensive characterization was performed to analyze the mechanical and thermal properties of the novel composites produced in order to identify the best composition to achieve the desired characteristics.
48 KAJIAN TEKNIKAL PENGHARMONIAN TEKNIK ANALISIS PENGAKTIFAN NEUTRON (NAA) Muhammad Azfar bin Azman, Zalina binti Laili, Md Suhaimi bin Elias, Nazaratul Ashifa binti Abdullah Salim, Azian binti Hashim, Shakirah binti Abd. Shukor, Siti Aminah binti Omar, Munirah binti Abdul Zali dan Muhammad Farhan bin Ridzuan ABSTRAK Teknik Analisis Pengaktifan Neutron (Neutron Activation Analysis) merupakan suatu teknik analisis yang mampu menentukan kepelbagaian unsur dalam pelbagai jenis bentuk sampel sama ada sampel alam sekitar mahupun sampel daripada industri (Peter Bode, 2017). Di Agensi Nuklear Malaysia, teknik ini berupaya untuk menganalisis hampir 30-40 unsur-unsur yang terdapat di dalam jadual berkala daripada unsur utama (major element) kepada unsur surihan (trace element). Kumpulan Aplikasi Kimia Analisis (ACA) menggunapakai Teknik ini dalam penentuan unsur di dalam sampel khidmat dan juga sampel kajian. Oleh itu, kertas kajian ini adalah suatu kajian teknikal untuk memurnikan kaedah teknik sedia ada untuk meningkatkan kecekapan yang lebih optimum dan sesuai dengan kaedah kerja sedia ada. Kajian dilakukan dengan menggunakan beberapa sampel bahan rujukan piawai serta sampel tanah dan flora sebagai sampel yang tidak diketahui. Kajian ini juga mengkaji kebolehan menggunapakai semula sampel yang telah disinarkan mengikut kepelbagaian tempoh masa.
49 THE DESIGN, FABRICATION AND INSTALLATION OF ULTRAVIOLET (UV) BOXES FOR NATURAL RUBBER LATEX VULCANIZATION Muhammad Hannan Bahrin, I. Sofian, C. K. Chai, M. L. Mohd Noorwadi, Anwar AbdulRahman, Siti Hajar Said, Wan Ismail Wan Yusof, Muhamad Nor Atan and B. N. M. Rizwan ABSTRACT According to scientific studies, ultraviolet radiation has the potential to be used in the pre- vulcanization of NRL. The photoinitiator and the coagent are two main components of UV prevulcanization. A photoinitiator is a compound that absorbs UV light and produces free radicalsthat initiate the cross-linking reactions. Meanwhile, a coagent is a compound that enhances the cross-linking efficiency by reacting with the free radicals and/or the rubber molecules. Figure 1: General mechanism of UV initiated thiol-ene reaction [Schlögl et al., 2010] Several factors can affect the outcome of UV prevulcanization, such as the type and concentrationof the photoinitiator and the coagent, the
50 duration and intensity of UV irradiation, the distance between the light source and the latex, the mixing time of the latex with the photoinitiator and thecoagent, the depth of the latex pool and the presence of oxygen, water, or other additives in the latex. These factors can influence the rate and extent of cross-linking reactions, as well as the properties and stability of the prevulcanized natural rubber (PVNR) latex. The existing UV prototype for natural latex vulcanization will be studied. Then, the design conceptwill be developed. The objective of this study is to provide specifications oftheUVbox prototype.This prototype will help to identify the suitable distance between the sample and the UV light. Thedistance between the formulated NRL sample and UV light will affect the NRL crosslink density and mechanical and physical properties. Therefore, several factors will affect the design of the UVbox prototype such asthe type of UV lamps, materials and sizes ofthe box, latex sample size, thesample position in the UV box, position of UV lamps, and design of electrical circuits. The detailsof fabrication cost and estimation of electricity usage are also discussed in this paper.
51 GEL CONTENT AND HOT SET TEST AS MAIN REQUIREMENTS FOR HEAT SHRINK TUBE IRRADIATION AT ALURTRON Mohd Suhaimi Jusoh, Ruzalina Baharin, Siti Zulaiha Hairaldin, Shahrina Akma Mansur, Noor Hasni M. Ali, Azmi Ali, Mohamad Hakiman Mohamad Yusoff, Mohamad Zulhailmee Mohd Zainal, Muhd Izham Ahmad, Harzawardi Hasim and Shalina Sheik Muhamad ABSTRACT The automotive industry is constantly evolving, with manufacturers seeking new and innovative ways to improve the performance, reliability, and safety of vehicles. One area of focus in this evolution is the crosslinking effect on wire, cables, and tubes through electron beam irradiation. Crosslinking, the process of chemically bonding polymer chains to form a three-dimensional network, has been widely studied and implemented in various industries. The use of electron beam irradiation for crosslinking in the automotive industry offers several advantages over traditional methods. Firstly, electron beam irradiation produces non-residue and non-carcinogenic gas, resulting in a fast and efficient crosslinking process. No after process treatment or quarantine needed. Secondly, the application of electron beam radiation from the high energy accelerator provides quick turnaround time production. Then, electron beam irradiation is a clean with on/off technology that gives good acceptance to the public. Wire, cables, and tubes play a critical role in connecting various electrical and electronic systems within the vehicle, ensuring smooth operation and communication between different components. As a country becomes increasingly reliant on electronic components for its automotive needs, the need for efficient and reliable wiring becomes even more crucial. The process of crosslinking, particularly through electron beam irradiation, has emerged as an effective method for enhancing the properties and performance of automotive wiring. Electron beam irradiation has been developed as a method of
52 crosslinking polymeric materials for various applications in the automotive industry. When exposed to the electron beam radiation, heat shrink tube polymer undergoes crosslinking that can be observed through gel content percentage and hot set value. They become the main element for ALURTRON, the electron beam irradiation facility in Nuclear Malaysia to confirm the crosslinking process of the customer product. Hot set test was done to measure the elongation of samples for static load at a fixed temperature. Gel content analysis is performed to determine the percentage of crosslink fraction in polymer. Therefore, in this work, we carried out a study on gel content and hot set data from heat shrink tubes that were irradiated at ALURTRON. The gel content value required by the customer fall within 65% to 75% while the hot set range is set at 60% to 98%. Correlation were made between both set of data from year 2017 to 2022.
53 ULTRAVIOLET IRRADIATOR PROTOTYPE FOR LATEX VULCANIZATION Chai Chee Keong, Sofian Ibrahim, Mohd Noorwadi Mat Lazim, Noor Mohd Rizwan Brahin, Khairul Hisyam Mohamed Yusop and Hafizuddin Maseri ABSTRACT Scientific studies have shown the capability of ultraviolet radiation in vulcanizing latex1,2 . Methods and ultraviolet radiation devices for latex vulcanization have been internationally patented3 . There are also publications about the use of thin layer photoreactor and falling film photoreactor for latex vulcanization using ultraviolet radiation4 . The patented and published designs for UV irradiation apparatus are shown in Figure 1 (a). Realizing the potential of ultraviolet radiation technology in latex vulcanization and its potential impact to the latex production and latex dipped product manufacturing industries in Malaysia, the Malaysian Nuclear Agency has endeavored to conduct research and development for a novel ultraviolet radiation technology, related expertise and devices. Laboratory studies have shown positive results in latex vulcanization using innovative latex formulation that is based on hybrid ultraviolet radiation – peroxide vulcanization. In order to benefit the related local industries, it is crucial to upscale the laboratory formulation and setup to demonstrate the feasibility and viability of these research findings beyond laboratory scale through a well-designed prototype. However, it is also important to ensure the novelty of the prototype to avoid patent infringement issues. This paper discusses the design of a pilot-scale ultraviolet irradiator prototype for latex vulcanization. This pilot-scale prototype will be used to test the feasibility of the laboratory findings and obtain preliminary data for industrial-scale prototype in the future.
54 IMPROVEMENT ON OZONE ELIMINATING SYSTEM FROM IRRADIATION VAULT MINTEC-SINAGAMA AGENSI NUKLEAR MALAYSIA Mohamad Suhaimi Yahaya, Mohd Khafidz Shamsuddin, Abdul Razak Hashim, Ahsanulkhaliqin Abdul Wahab, Hamzah Abu Bakar and Saifol Hisham Ghani ABSTRACT MINTec-Sinagama Irradiation Plant is one of the main irradiation facilities in Malaysian Nuclear Agency and uses Gamma radiation from a Cobalt-60 source to irradiate various products such as medical products and packaging materials. The gamma irradiation process produces ozone.Ozone is a highly oxidizing gas and harmful to human. Because of that, the ventilation system is used to remove ozone from the Sinagama Vault to the atmosphere at high altitude as shown in figure 1 below. Previous ventilation system design was ineffective due to the blockage at ventilation path at building roof after installation of wire mesh during the work of preparing an insect-free area for the purpose of irradiation rambutan for export to USA. Therefore, ozone was trapped inside the building and been circulated inside the Sinagama building as reported by the plant operator. This paper will describe the improvement work that has been done to remove the ozone from the building. Figure 1. Existing ventilation duct goes up to building roof
55 KEUPAYAAN PERALATAN PEMESINAN DI PDC Anwar bin Abdul Rahman, Salim bin Hassan, Mohd Azam Safawi bin Omar, Muhammad Ibrahim bin Mohd Aminuddin, Mohd Rizal bin Mamat @ Ibrahim, Azraf bin Azman, Mohd Zaid bin Hassan@Abdul Rahman dan Muhammad Hannan bin Bahrin ABSTRAK Pusat Pembangunan Loji dan Prototaip adalah unit dibawah Bahagian Sokongan Teknikal yang menyediakan perkhidmatan rekabentuk kejuruteraan dan fabrikasi kepada pelanggan dalaman dan luar Agensi Nuklear Malaysia. Perkhidmatan utama yang disediakan oleh PDC adalah membangunkan projek projek prototaip, sistem automasi dan juga memberikan perkhidmatan dalam membangunkan loji loji rintis dan penyinaran. Perkhidmatan ini dilaksanakan sejak tahun 1982, bermula dengan penempatan mesin mesin kayu serta mesin manual konvensional manakala rekabentuk menggunakan papan lukisan yang juga dilukis secara manual menggunakan kemahiran individu. Sehinggalah kepada permodenan kemudahan kejuruteraan dengan pengenalan kepada mesin separa CNC dan rekabentuk berbantukan komputer (CAD) yang bermula sejak tahun 1990. Sehingga kini, PDC berterusan memberikan perkhidmatan yang cemerlang dalam menyediakan perkhidmatan kepada pelanggan sedia ada. Bengkel kejuruteraan salah satu kemudahan yang terdapat di PDC memberikan perkhidmatan pemesinan yang menggunakan mesinmesin konvensional manual, mesin CNC (Computer Numerical Control), kimpalan, mesin pembentukan dan mesin pemotongan. Ini termasuklah kepada penggunaan relau yang berkemampuan untuk tuangan plumbum sehingga 200kg. Bengkel kejuruteraan dikendalikan oleh 3 orang Penolong Jurutera dan 9 orang kakitangan berkemahiran tinggi.
56 OPTIMIZATION OF THE OPERATION INLET FLOW RATE FOR A MULTIPHASE SEPARATION TANK Muhammad Anas bin Mat Marzuki ABSTRACT This paper investigates the optimization of the operation inlet flow rate for a multiphase separation tank, aiming to improve its efficiency and performance. Multiphase separation tanks play a critical role in various industries such as oil and gas, wastewater treatment, and chemical processing, where the separation of different phases (e.g., oil, gas, and water) is essential for production and environmental considerations. The paper highlights the significance of the operation inlet flow rate as a key parameter affecting the separation efficiency and overall system performance. It explores the challenges associated with determining the optimal flow rate, considering factors such as fluid properties, tank geometry, operating conditions, and desired separation targets. The optimization technique leveraging computational fluid dynamics (CFD) is used as the approach for optimizing the flow rate in different scenarios. By addressing the optimization of the operation inlet flow rate, this paper contributes to the optimization of multiphase separation technology in general. It provides a comprehensive overview of existing methodologies, identifies research gaps, and proposes future directions for further improvements. The findings of this study have practical implications for industries relying on multiphase separation tanks, offering guidance for enhancing operational efficiency. In conclusion, this paper underscores the significance of optimizing the operation inlet flow rate for multiphase separation tanks. By leveraging advanced modelling techniques and control strategies, the efficiency and effectiveness of these vital separation systems can be significantly improved, leading to enhanced operational performance across various industrial sectors. Keywords: Optimization, Separation Tank, Computational Fluid Dynamic
57 IMPROVEMENT ON VENTILATION SYSTEM IN CONTROL ROOM FOR MEDICAL PHYSICS LABORATORY (MPL) BLOCK 32T AGENSI NUKLEAR MALAYSIA Mohamad Suhaimi Yahaya, Nordin Salleh, Mohd Khafidz Shamsuddin and Saifol Hisham Ghani ABSTRACT Medical Physics Laboratory (MPL) is a facility under Kumpulan Metrologi Sinaran (KMS), Radiation Health and Safety Divion (BKS). MPL provides services of medical diagnostic x-ray apparatus, lead equivalentthicknesstestfor medical x-ray room and the dose calibrator calibration in nuclear medicine using some of laboratories located in Block 32T. Since 2019, BKJ receives the complaint from MPLs' staffs regarding poor ventilation in calibration laboratory (32B002), bunker (32B003) and control room (32B001) located at Block 32T. The cooling system, generator and control panel for x-ray machine are located in control room. Moreover, some of these equipments produce excessive heat during operation. Poor ventilation in these laboratories and rooms has cause inconvenient among the staffs. Therefore, there are some situation which is the staff have to open the bunker door while operating the equipment from control room to make themself comfortable. This action was not advisable because it will expose them to high level of radiation. In addition, poor ventilation and high humidity levels in laboratories and bunkers can cause problems with x-ray machines and their accessories. Several discussions have been conducted in order to improve the ventilation system. Fortunately, KMS group has received development expenditure (DE) budget under the Twelfth Malaysia Plan (RMKe12) 2nd rolling plan for upgrading theirlaboratories and facilities. This paper will describe the actionsthat have been taken to improve the ventilation system in the MPL laboratories Block 32T. Figure 1. MPL laboratory, bunker and control room in Block 32T
58 SISA RADIOAKTIF JENIS PUNCA TERPAKAI (DSRS): CABARAN DAN LALUAN KE HADAPAN Nariman bin Md Mashor@Mansor, Nurul Wahida binti Ahmad Khairuddin, Kang Wee Siang, Mohammad Nizammuddin bin Abd. Aziz; Mohd Zahiruddin bin Jaafar, Mohd Na'imullah bin Ab Razak, Nurayu binti Ibrahim dan Norfazlina binti Zainal Abidin ABSTRACT Waste Technology Development Centre (WasTec), Malaysian Nuclear Agency was given a responsibility to provide services for managing radioactive waste at the national level. This centre performs all radioactive waste management activities according the procedures and requirement as set by the regulatory body. In 2022, WasTeC provided services for the dismantling and disposal of disused sealed radioactive sources(DSRS) from the cement factory known as Lafarge Rawang Plant, Selangor. The plant stopped its operation in 2019 and WasTeC is participated in the activity to identify and dismantled the DSRS located in the plant. In total, 9 units DSRS for disposal consist of 4 units Fe22, 2 units of Pu 238 and 3 units of Cf 252 with an accumulated activity equal to 619 mCi. Based on the site visit, there were 7 units of DSRS still attached in an equipment while the remaining are stored in the drums. The surrounding working area wasfound dusty, an old building structure as well as limited space for dismantling activities. This paper will discuss on procedures, activities and challenges during dismantling and disposal of the DSRS. ABSTRAK Pusat Pembangunan Teknologi Sisa (WasTeC), Agensi Nuklear Malaysia bertanggungjawab untuk memberi khidmat pengurusan sisa radioaktif di peringkat kebangsaan dan memastikan kesemua aktiviti adalah mengikut keperluan yang telah ditetap oleh badan penguatkuasa. Pada tahun 2022, WasTeC telah memberi khidmat penanggalan dan
59 pelupusan sisa radioaktif dari kilang simen iaitu Lafarge Rawang Plant, Selangor.Kilang tersebuttelahditamatkanoperasipadatahun2019,oleh yang demikian khidmat WasTeC diperlukan untuk mengenalpasti sisa radioaktif yang masih ada di kemudahan tersebut serta menilai keadaan kawasan tapak sebelum aktiviti penanggalan DSRS dilakukan. Sisa yang dilupuskan adalah sisa radioaktif jenis punca terkedap terpakai (DSRS) iaitu sebanyak 9 unit. Ia terdiri dari 4 unit Fe55, 2 unit Pu238 dan 3 unit Cf252 dengan jumlah aktiviti sebanyak 619.98 mCi. Berdasarkan hasil lawatan tapak, terdapat 7 unit punca radioaktif masih terdapat di dalam mesin/alat manakala 2 unit di dalam tong drum. Persekitaran tapak kerja didapati berdebu, struktur bangunan uzur serta ruang kerja untuk aktiviti penanggalan yang terhad. Kertas kerja ini akan membincangkan berkenaan prosedur, aktiviti serta cabaran yang dihadapi semasa aktiviti penanggalan dan pelupusan DSRS ini dilaksanakan Kata kunci: DSRS, pengkondisian, penanggalan
60 PEMETAAN DOS PENYINARAN GAMA (CO-60 RAK 1) DI SINAGAMA Syuhada Ramli, Cosmos George, Ahsanulkhaliqin Abdul Wahab, Mohd Rizal Md. Chulan, Hasan Sham, Ahmad Zainuri Mohd Dzomir dan Zarina Mohd Nor. ABSTRAK Sinagama ialah kemudahan penyinaran gama dalam pelbagai aplikasi untuk penyinaran produk pada pelbagai julat dos. Penyinaran gamma di Sinagama berasaskan sumber Co-60 dengan proses penyinaran dijalankan berkadaran dengan masa berdasarkan permintaan dos oleh pihak pelanggan. Bagi tujuan pengeksportan buah-buahan segar ke United State of Amerika (USA), julat dos sinaran diperlukan bagi menghapuskan atau merencatkan perkembangan serangga perosak adalah 400 – 1000 Gy. Untuk mencapai dos berikut, hanya sumber Co60 rak 1 sahaja digunakan berbandingpenyinarandarisumberCo-60 rak 1 dan 2 iaitu bagi kebanyakan produk yang dihantar ke Sinagama untuk rawatan nyahkuman dan pensterilan dari julat 5 – 25 kGy. Pemetaan dos diperlukan untuk mewujudkan parameter operasi loji, keseragaman dos, kecekapan penggunaan sumber Co-60 dan kedudukan dos maksimum dan minimum. Semua data untuk dos maksimum dan minimum yang diperoleh daripada laporan pemetaan dos boleh digunakan untuk memantau dan meramalkan kedudukan dos maksimum (Dmax) dan dos minimum (Dmin) yang akan diterima di seluruh tote semasa proses penyinaran produk.
61 STUDY ON CHILLER REPLACEMENT WORKS FOR CENTRALISED AIR CONDITIONING SYSTEM IN AGENSI NUKLEAR MALAYSIA Mohamad Suhaimi bin Yahaya, Hamzah bin Abu Bakar and Muhammad Nizam bin Othman ABSTRACT Chillers for centralised air conditioning system in Agensi Nuklear Malaysia have been operated for 20 to 35years. There are 5 chillers where 3 chillers are located in Block 27, and 1 chiller located in Block 42 and 44 respectively. With good practice, operating and maintaining chiller have been going forsuch a long time than its expected life cycle. However, those chillers need to be replaced with new chiller due to outdated technology and inefficiency for energy consumption. This paper willdescribe the reason for chiller replacement and also the proposal works to obtain reduction in electricity consumption. As a conclusion, all of chillersin Agensi Nuklear Malaysia need to be replaced in order to support R&D activities and for reduction of electricity consumption. Keywords: chiller, energy consumption ABSTRAK Mesin pengokol untuk sistem penghawa dingin berpusat di Agensi Nuklear Malaysia telah beroperasi selama 20 hingga 35 tahun. Terdapat 5 mesin pengokol di mana 3 terletak di Blok 27, dan 1 mesin pengokol terletak di Blok 42 dan 44 masing-masing. Dengan amalan yang baik, mengendalikan dan menyelenggara penyejuk telah berjalan begitu lama daripada kitaran hayat yang dijangkakan.Walau bagaimanapun, mesin pengokol tersebut perlu diganti dengan penyejuk baharu kerana teknologi yang lapuk dan ketidakcekapan penggunaan tenaga. Kertas kerja ini akan menerangkan sebab penggantian mesin pengokol dan juga cadangan berfungsi untuk mendapatkan pengurangan penggunaanelektrik. Kesimpulannya, semua mesin pengokol di Agensi Nuklear Malaysia perlu diganti untuk menyokong aktiviti R&D dan pengurangan penggunaan elektrik. Kata kunci: pertukaran maklumat cekap dan selamat, cabaran perubahan teknologi, komunikasi terpadu
62 PENGAJARAN DARIPADA REKA BENTUK PERISAI PELINDUNG DSRS DAN PINTU PLUMBUM Nor Mohd Zaid bin Hassan@Abdul Rahman, Muhammad Hannan bin Bahrin, Mohd Rizal bin Mamat @ Ibrahim, Azraf bin Azman, Anwar bin Abdul Rahman, Rohyiza binti Ba'an dan Mohd Zamry bin Zakariah ABSTRAK Kertas kerja ini menerangkan tentang pengajaran yang diperolehi daripada reka bentuk perisai pelindung DSRS dan pintu plumbum. Ia bermula dengan penilaian reka bentuk perisai pelindung yang meliputi gred konkrit, besi cerucuk dan kaedah sambungan dan penuangan konkrit. Seterusnya adalah reka bentuk pintu plumbum dengan mengambil kira bebanan plumbum, dan struktur besi termasuk pemilihan automasi operasi yang berkaitan. Kaedah angkatan, pengangkutan dan pemasangan pintu plumbum akan memberi kesan lenturan pada struktur pintu. Hal ini akan memberi kesan kritikal terhadap nilai jurang dan selisih diantara pintu dan dinding perisai pelindung. Kertas kerja ini akan mengupas secara terperinci cabaran yang dihadapi termasuk langkah-langkah pencegahan yang telah dijalankan bagi memastikan reka bentuk perisai pelindung DSRS dan pintu plumbum ini memenuhi piawaian keselamatan yang telah ditetapkan. Ia akan menjadi rujukan dalam penghasilan reka bentuk perisai pelindung dan pintu plumbum yang akan datang. Kata kunci: Perisai pelindung, pintu plumbum, jurang, selisih
63 PENGUJI RELAY LOJI RUMAH HIJAU GAMA (GAMMA GREEN HOUSE RELAY TESTER) Saipo Bahari bin Abdul Ratan, Izuhan bin Ismail, Mohd Hazri bin Mohd Salleh, Mazlipah binti Mohamed Ramlan, Muhammad Na'qiuddin Isma dan Mohamad Azwan Nizam bin Mohd Nasir ABSTRAK Penguji relay ini dibangunkan apabila loji ini kerap mengalami kerosakan. Apabila loji mengalami kerosakan, bebanan yang terpaksa ditanggung apabila proses mengenalpasti punca kerosakan dilakukan. Terdapat beberapa alatan yang perlu diuji antaranya Peranti Pelindung Surge (SPD), Relay, Bekalan Kuasa 5V, Bekalan Kuasa 12V & Bekalan Kuasa 24V, Pengujian Sistem Pneumatic. Alat uji ini berfungsi untuk mengenalpasti kebolehfungsian relay. Dalam kaedah biasa pengujian dilakukan dengan menggunakan bekalan kuasa DC dan multimeter yang digabungkan secara selari. Pengujian ini dilakukan untuk mengetahui samaada coil bekalan kuasa relay dan keluaran relay berfungsi dengan baik. Penguji relay ini dapat memberitahu penguji tiga (3) keadaan relay. Keadaan pertama, iaitu apabila LED MERAH dan LED HIJAU menyala dengan terang, relay berfungsi dengan baik. Keadaan kedua pula adalah LED MERAH dan LED HIJAU Malap, relay tidak berfungsi dengan baik. Keadaan ketiga adalah apabila LED HIJAU dan LED MERAH tidak menyala, relay rosak. Ketiga – tiga keadaan ini mempengaruhi fungsi Loji apabila relay ini dipasang pada sistem. Kaedah biasa pengujian relay agak rumit dan mengambil masa yang agak lama dan ada risiko tidak tepat. keadaan ini terjadi kerana keadah biasa hanya menguji fungsi coil dengan mengalirkan bekalan kuasa DC dan fungsi keluaran dengan menggunakan julat Ohm untuk mengetahui rintangan pada pin keluaran relay. Kesilapan juga boleh terjadi apabila menguji relay dalam kuantiti yang banyak.
64 CABARAN DAN PENGALAMAN DALAM KERJA PENYENGGARAAN INSTRUMENTASI SEPANJANG PERKHIDMATAN DI AGENSI NUKLEAR MALAYSIA Ramzah bin Mohamed ABSTRAK Pembentangan ini membincangkan cabaran dan pengalaman peribadi sepanjang perkhidmatan di dalam kerja-kerja penyenggaraan peralatan instrumentasi. Perkongsian ini diharap dapat memberi maklumat dan cadangan yang berguna kepada pegawai-pegawai generasi baru di Agensi Nuklear Malaysia. Kata kunci: Penyenggaraan peralatan instrumentasi
65 DESIGN AND DEVELOPMENT OF TEMPERATURE MONITORING USING ARDUINO UNO FOR HPGe DETECTOR APPLICATION Noor Farhana Husna A Aziz, Saipo Bahari Abdul Ratan, Maslina Mohd Ibrahim, Mohd Hazri Mohd Salleh, Ain Hafizatul Abi Talib and Muhammad Afiq Hakimi Mohd Rahime ABSTRACT High-resolution gamma spectroscopy plays a important role in nuclear security applications, primarily because of its exceptional energy resolution capabilities. The High Purity Germanium (HPGe) detector, known for its ability to analyze and quantify gamma-emitting radioisotopes with high precision, is frequently employed for this purpose (Mc Cabe, 2015). Within the Malaysian Nuclear Agency, more than 30 gamma spectroscopy instruments are utilized for sample analysis and research, and the responsibility for their maintenance falls underthe purview ofthe Automation and Instrumentation Centre (AIC). The maintenance includes diagnosing and repairing the HPGe detectors. One of the challenges with HPGe involves the failure of the cooling process to operate properly, resulting in an inability to reach the desired temperature of -160 oC. Typically, liquid nitrogen-cooled detectors, achieve sufficient cooling within four to six hours after being filled with liquid nitrogen. Cooling the detector to the temperature of liquid nitrogen (-77K) serves the purpose of reducing thermal noise, thus minimizing leakage current (Tawade et.al 2021). But, HPGe requires a longer cooling process when it is damaged. This process necessitates constant monitoring of temperature changes with time taken for cooling. This can disrupt other work processes. Therefore, with the presence of this temperature monitoring system, temperature monitoring and data recording can be done automatically, making it easier for employees to monitor without disrupting their work time. This paper introduces the design and development of a temperature monitoring system tailored for HPGe detectors based on Arduino
66 technology, incorporating a secure digital (SD) card and real-time lock (RTC) module, along with a liquid crystal display (LCD) as depicted in Fig. 1(a). Figure 1 (a) Block diagram (b) Data interpolation of resistance and temperature of the FET
67 PENGHASILAN SELONGSONG METER TINJAU Muhammad Ibrahim bin Mohd Aminuddin, Harfidzul Faidzal bin Haris, Mohammad Hafiz bin Bakri, Muhammad Fazriq bin Mohd Fadzil, Mohd Azam Safawi bin Omar, Salim bin Hassan, Azraf bin Azman, Anwar bin Abdul Rahman, Mohd Rizal bin Mamat @ Ibrahim, Mohd Zaid bin Hassan@Abdul Rahman dan Muhammad Hannan bin Bahrin ABSTRAK Penghasilan prototaip selongsong meter tinjau ini melibatkan rekabentuk serta proses pembikinan menggunakan kaedah pemesinan konvensional dan moden. Rekabentuk selongsong ini bergantung pada rekabentuk papan litar elektronik yang telah dibangunkan. Perisian rekabentuk CAD, perisian EdgeCAM, mesin pengisar konvensional dan mesin pengisar CNC digunakan semasa pembikinan selongsong ini. Kertas kerja ini akan membincangkan berkenaan proses pembikinan serta penghasilan selongsong meter tinjau. Kata kunci: Rekabentuk selongsong, Prototaip, Pengaturcaraan CNC, Mesin CNC, Mesin Pengisar ABSTRACT The production of the prototype enclosure for the survey meter includes the design and manufacturing process using conventional and modern machining methods. The design of this enclosure depends on the design of the developed electronic circuit board. Inventor software for CAD, EdgeCAM software, conventional milling machines, and CNC milling machines are used in the manufacturing of this enclosure. This paper discusses the manufacturing process and production of the survey meter enclosure.
68 PENGOPERASIAN KEMUDAHAN ALAT MUDAH ALIH (MOBILE TOOL KIT FACILITY – MTKF) UNTUK PENGKONDISIAN SISA PUNCA TERKEDAP TERPAKAI(DSRS) KATEGORI 3-5 DI AGENSI NUKLEAR MALAYSIA Mohd Na'imullah bin Ab Razak, Nurul Wahida binti Ahmad Khairuddin dan Kang Wee Siang ABSTRAK Pengurusan sisa radioaktif adalah merupakan satu isu penting yang melibatkan penggunaan tenaga atom secara aman di Malaysia. Di Malaysia, sumber radioaktif terkedap digunakan secara meluas terutamanya dalam bidang industri, pertanian, perubatan dan penyelidikan. Kertas kerja ini menerangkan pengalaman dan aktiviti yang dilakukan di Pusat Pembangunan Teknologi Sisa (WasteC) sepanjang tempoh pengkondisian sisa punca terkedap terpakai (DSRS) menggunakan Kemudahan Alat Mudah Alih atau 'Mobile Tool Kit Facility (MTKF)'. MTKF adalah satu kemudahanyang direka khas yang dilengkapi dengan alat peralatan pengkondisian dan mesin kimpalan untuk menjalankan operasi pengkondisian DSRS dan pelupusan lubang gerek khususnya untuk sisa DSRSkategori 3-5. Sebanyak 13137 unit DSRS telah berjaya dikondisikan di MTKF dengan jumlah keseluruhan aktiviti sebanyak 25.6 Ci. Kesemua sisa ini dimasukkan ke dalam 42 bekas pelupusan sisa atau 'Source Disposal Container (SDC)' untuk tujuan pelupusan di kemudahan lubang gerek (Borehole Disposal Facility). Ini melibatkan inventory sisa bagi 15 radionuklid iaitu Pm147, Fe55, Cd109, Tl204, Po210, Co60, Co57,Ni63, Kr85, Sr90, Cs137, Se75,Na22, Bi207 dan Am241. Prinsip ALARA digunakan ketika melakukan aktiviti ini bagi memastikan pengoptimuman perlindungan radiasi dikekalkan pada aras serendah munasabah terhadap kakitangan yang terlibat. Kata kunci: DSRS, pengkondisian, penanggalan
69 ABSTRACT Radioactive waste management is an important issue involving the peaceful use of atomic energy in Malaysia. These sources become radioactive waste after used. In Malaysia, sealed radioactive sources are widely used in industry, agriculture, medicine and research. This paper describes the conditioning experiences and activities using The Mobile Tool Kit Facility (MTKF). MTKF is a facility specially designed for carry out DSRS conditioning and borehole disposal operations which equipped with standard items and welding machine for DSRS category 3-5. The total number of DSRSsto be disposed is 13137 units with total activity of 25.6 Ci have been conditioned in 42 sourcedisposal containers (SDC). The inventory consists of 15 radioisotopes namely Pm 147 , Fe 55 , Cd 109 , Tl 204 , Po 210 , Co 60 , Co 57 , Ni 63 , Kr 85 , Sr 90 , Cs 137 , Se 75 , Na 22 , Bi 207 and Am241 . The ALARA principle is used when performing this activity to minimize the radiation doses as low as reasonably achievable. Keywords: Mobile tool kit facility, disused radioactive sources, borehole disposal