https://jsnm.nuclearmalaysia.gov.my/index.php/dja/issue/feed 2025-08-14T09:19:30+08:00 Dr. Siti Najila Mohd Janib najila@nuclearmalaysia.gov.my Open Journal Systems <p>Jurnal Sains Nuklear Malaysia (JSNM; Nuclear Science Journal of Malaysia) is a refereed journal published biannually since 1983 by the Malaysian Nuclear Agency. </p> <p>JSNM is dedicated to providing a platform for publication of articles on the development and applications of the peaceful uses of nuclear technology and radiation applications. It is a multidisciplinary, international, peer-reviewed open access journal for original scientific papers in fundamental and applied research as well as review articles related to nuclear science and technology. </p> <p>The journal aims to serve the scientific and academic community, industry professionals, research institutions, government agencies and policy-makers by:</p> <ul> <li>Providing authoritative and up-to-date information in the field of nuclear science and technology</li> <li>Promoting the exchange of ideas and research within the nuclear science and technology community</li> <li>Supporting the development of nuclear technology and applications in various fields for peaceful purposes</li> </ul> <p>We welcome submissions that explore the following topics:</p> <ol> <li>Nuclear engineering and management</li> <li>Medical technology and health physics</li> <li>Industrial applications</li> <li>Agrotechnology and biosciences</li> <li>Water, energy and environment</li> <li>Radiation processing technology</li> <li>Radiation safety, security and health</li> <li>Mathematics, computer science and information technology</li> </ol> https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/144 2025-02-25T14:48:02+08:00 Julie Andrianny Murshidi julie@nm.gov.my

<p><em>Ti-Mn alloy compounds with the composition TiMn₂, Ti_0.97Zr_0.019Mn_1.5Cr_0.57and Ti_0.7875Zr_0.2625Mn_0.8Cr_1.2were synthesised by mechanical alloying technique. An amorphous Ti-Mn alloy was formed when the starting reagents were mechanical alloying for 40 h. The corresponding crystalline phase TiMn was formed when the amorphous alloy was annealed at 800°C. The addition of a process control agent (Toluene) leads to the formation of a carbide phase (TiC) in the samples. The presence of impurities, carbide (TiC) and oxide (TiO) phases resulted a decrease in C14 laves phase wt.% in the synthesised samples. Only 37.24, 31.5 and 32.81 wt.% C14 phase were formed in TiMn₂, Ti_0.97Zr_0.019Mn_1.5Cr_0.57and Ti_0.7875Zr_0.2625Mn_0.8Cr_1.2</em>respectively<em>. The result also showed that the theoretical value of 1.9 hydrogen wt.% could not be reached by these samples.</em></p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/117 2025-01-08T23:06:49+08:00 Sapizah Rahim sapizah@nm.gov.my Syaza Adani Ahmad Shahrul Aimee2 sapizah@nm.gov.my Siti Nur Najihah Meor Kamarulzaman sapizah@nm.gov.my Ilhan Shah Amran sapizah@nm.gov.my Khairul Anuar Mohd Salleh khairul_anuar@nm.gov.my Arshad Yassin sapizah@nm.gov.my Mohd Junaidi Jaapar sapizah@nm.gov.my

<p><em>An exposure chart serves as a critical tool for correlating exposure time with the strength of the radiation source and the thickness of the material being tested. It aims to ensure consistent image quality across various examinations and imaging systems. Traditionally, exposure charts were designed for X-ray machines that utilized film as the imaging medium. However, with the advent of digital imaging, imaging plates (such as those used in Computed Radiography systems) have replaced films, allowing for the creation of digital images. These digital images can be electronically stored, eliminating the need for physical film storage and streamlining image retrieval processes. While digital imaging has significantly advanced the field, comprehensive exposure charts specifically tailored for phosphor imaging plates in industrial applications are still lacking. This study addresses this gap by creating an exposure chart using a steel step wedge and a white imaging plate (equivalent to D7 film) for the Isovolt Titan E x-ray machine. To calibrate the system, we determine the minimum gray value (GVmin) and energy using a copper step wedge at a focal-detector distance of 100 cm and an energy level of 180 kV. Each step wedge is exposed to varying energy levels and constant current until the desired gray value is achieved. Subsequently, we construct an exposure chart based on steel thickness (measured in millimeters). By comparing the film and developed exposure charts, we evaluate their performance using welded plates. The results demonstrate that an exposure chart can indeed be developed for phosphor imaging plates. Furthermore, the computed radiography system significantly reduces exposure time (by approximately 80%), making it quantitatively comparable to conventional film radiography.</em></p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/121 2024-11-10T02:27:06+08:00 Muniroh Md Saad muniroh@nm.gov.my Norazlina Noordin azlina@nm.gov.my Mustapha Akil mustapha@nm.gov.my Shakinah Salleh shakinah@nm.gov.my Norhafiz Talib norhafiz@nm.gov.my Zaki Hussain zaki_hussain@nm.gov.my Muhammad Abu Bakar muniroh@nm.gov.my Muhammad Syamim Abdul Rahim muniroh@nm.gov.my Noor Shaireen Shahira Khalid muniroh@nm.gov.my

<p>Cassava (Manihot esculenta Crantz) is one of the most essential carbohydrate crops worldwide, consumed by millions of populations in Africa, Asia, and Latin America (Parmar <em>et al.</em>., 2017). Cassava (Manihot esculenta Crantz) is one of the most essential carbohydrate crops worldwide, consumed by millions of populations in Africa, Asia, and Latin America (Parmar <em>et al.</em>., 2017). Cassava (Manihot esculenta Crantz) is one of the most essential carbohydrate crops worldwide, consumed by millions of populations in Africa, Asia, and Latin America (Parmar <em>et al.</em>., 2017). <em>Cassava, known scientifically as Manihot esculenta is one of the most essential carbohydrate crops worldwide, consumed by millions of populations in Africa, Asia, and Latin America. In Malaysia, Cassava produces various food items, including tapioca pearls, and cassava chips. Over the past two decades, advancements in mutation breeding techniques have significantly contributed to the genetic improvement of cassava, addressing challenges such as low yield, disease susceptibility, and poor nutritional content. Additionally, mutation breeding has facilitated the enhancement of root quality, including higher starch content and improved cooking properties. Cassava stem cuttings were exposed to various gamma irradiation dose rates (0.07 to 2.67 Gy/hour) over eight weeks. The results showed that survival rates remained high across most treatments, indicating cassava's resilience to radiation. However, plant height and bud formation were adversely affected by higher doses, with the highest cumulative dose (1709.49 Gy) resulting in the lowest plant height (30.4 cm) and reduced bud counts. Morphological changes, such as chlorophyll degradation and leaf abnormalities, were prevalent at higher doses. This suggests that while cassava can tolerate significant gamma irradiation, substantial doses impede growth and induce notable morphological mutations. Future research should focus on the growth of subsequent mutant generations to further understand the long-term impacts of chronic gamma irradiation on cassava.</em></p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/147 2025-02-26T14:28:56+08:00 Mohamad Hairie Rabir m_hairie@nuclearmalaysia.gov.my Mark Dennis Usang mark_dennis@nm.gov.my Muhammad Khairul Ariff Mustafa mkariff@nm.gov.my Julia Abdul Karim julia@nm.gov.my Mohamad Amirudin Mohamad Rosli amirudin@nm.gov.my

<p>This study aims to predict the source term and decay heat of highly burned-up fuel from the RTP TRIGA reactor, a critical factor for ensuring safe handling and disposal. Data on the reactor's operational history and accumulated burnup were collected and analyzed. Burnup calculations were carried out using the TRIGLAV code, while nuclide inventory simulations were performed with the MCNPX code. The decay heat was also evaluated using MCNPX. The gamma radiation strength for a core case and the decay heat resulting from energy deposition within the spent fuel pool were assessed. Additionally, the conservative maximum source term for a single fuel element was determined, highlighting the contribution of gamma radiation from radionuclides to decay heat in surrounding materials. This study provides vital data on the source term and decay heat, supporting the safe management of spent fuel from the TRIGA reactor.</p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/146 2025-02-26T09:15:21+08:00 Mohamad Hairie Rabir m_hairie@nuclearmalaysia.gov.my Mark Dennis Usang mark_dennis@nm.gov.my Julia Abdul Karim julia@nm.gov.my

<p>Micro Modular Reactors (MMRs) are gaining significant attention in the nuclear power industry due to their compact design and mobility. However, the challenge of optimizing neutron economy in such reactors remains a critical issue. To address this, advanced fuel designs with higher fissile density are being explored to extend the operational cycle length of MMRs. This paper presents a detailed neutronics simulation of an MMR using High-Fissile-Density Fuel. A High Temperature Reactor (HTR)-based MMR was selected as the reference model. Several case studies involving different High-Fissile-Density Fuel types were conducted, analyzing key neutronic parameters such as cycle length, achievable burnup, power distribution, and nuclide inventory. The simulations also examined the fuel temperature reactivity coefficient to assess the safety and efficiency of the proposed fuels. Thermal power generation and thermal-hydraulic behavior were not considered in this study and are left for future work. Results indicate a significant improvement in cycle length and burnup with the implementation of High-Fissile-Density Fuel, along with a more favorable power distribution. These findings suggest that advanced fuel designs could play a crucial role in enhancing the performance and sustainability of MMRs, contributing to the advancement of small nuclear reactor technologies.</p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA https://jsnm.nuclearmalaysia.gov.my/index.php/dja/article/view/139 2025-01-27T10:49:11+08:00 Khaironie Mohamed Takip khaironie@nm.gov.my Roshasnorlyza Hazan roshasnorlyza@nm.gov.my Nur Aqilah Sapiee nuraqilah@nm.gov.my Jacqueline Kones jacqueline@nm.gov.my Norhazirah Azhar norhazirah@nm.gov.my Wilfred Paulus wilfred@nm.gov.my Nor Asniza Ariffin khaironie@nm.gov.my Muhammad Faiz Fadzel khaironie@nm.gov.my

<p><em>Rare earth elements (REEs) have become increasingly influential in human lives due to their significant roles in various high-tech applications. The research on neodymium (Nd) and dysprosium (Dy) recovery from either primary or secondary REE sources has attracted the increasing attention of researchers because of their importance and indispensable in the manufacturing of neo magnet or NdFeB. Solvent extraction after acid leaching is commonly applied to extract and separate Nd and Dy from different sources. Therefore, a study was conducted to recovery Nd and Dy from local xenotime minerals through solvent extraction. This research aimed to determine the ability of acetic acid (CH₃COOH) as the leaching solution for the recovery of Nd and Dy using an organic solvent, 30% of Di-(2-ethylhexyl) phosphoric acid (D2EHPA) in kerosene as the extractant. The Nd and Dy concentrations before and after extraction were analysed using Energy Dispersive X-Ray Fluorescence (EDXRF). The study found that the highest extraction efficiency of Nd and Dy was 99.4% and 99.3%, respectively, at the leaching solution concentration of 1M and the volume ratio of the aqueous-to-organic (A/O) phase equal to 1. The best extraction temperature and time with the optimum extraction efficiency was at 30°C and 20 min. Therefore, this study proves that CH₃COOH is potentially be used as the leaching media of xenotime for the extraction of Nd and Dy with D2EHPA.</em></p>

2025-08-14T00:00:00+08:00 Copyright (c) 2025 JURNAL SAINS NUKLEAR MALAYSIA