Hybrid journal (It can contain Open Access articles) ISSN (Print) 1741-6361 - ISSN (Online) 1741-637X Published by Inderscience Publishers[439 journals]
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Authors:Muayad Mohammed Abed, Sarah M. Obaid, Duaa A. Salim Pages: 1 - 17 Abstract: The estimation of (<SUP align=right>222</SUP>Rn, <SUP align=right>226</SUP>Ra, and <SUP align=right>238</SUP>U concentrations in human blood is very important to assess the radiation exposure. The fission track method is used to detect alpha emitters in the blood of patients with kidney failure in Najaf, Iraq. The study found that uranium concentrations in renal failure blood tests ranged from 1.507 ± 0.24 ppb to 0.104 ± 0.41 ppb in non-smokers, while radon concentrations ranged from 8.763 ± 0.00246 Bq/m³ to 0.61 ± 0.0606 Bq/m³, and radium concentrations from 0.353 Bq/m³ to 0.024 Bq/m³. In contrast, healthy non-smokers had uranium concentrations between 1.014 ± 0.23 ppb to 0.078 ± 0.36 ppb, radon concentrations between 5.897 ± 0.012 Bq/m³ to 0.457 ± 0.071 Bq/m³, and radium concentrations between 0.237 Bq/m³ to 0.018 Bq/m³. The study found that individuals with renal failure have higher alpha emitter levels, 1.5 times higher than the healthy group, and these levels increase with age and are higher in women. Keywords: alpha emitters concentrations; fission track technique; blood samples; renal failure Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 1 - 17 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139127 Issue No:Vol. 17, No. 1 (2024)
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Authors:Abdulhussein A. Alkufi, Mohanad H. Oleiwi, Ali Abid Abojassim Pages: 18 - 27 Abstract: In this work, radon concentrations (<SUP align=right>222</SUP>Rn) for smokers in the Najaf Governorate /Iraq in some biological samples (serum of blood and urine) were measured using a RAD-7 detector (Durridge Company Inc, made in the USA). Fifty samples of serum blood (twenty-five (25)) and urine (twenty-five (25)) were collected for smokers and people aged (21-70) years for all samples. Samples were classified into five age groups (21-30), (31-40), (41-50), (51-60) and (61-70) to compare the results and determine their effects on the radon concentrations. The average value of radon concentrations in (Bq/m³) unit was (11.82±3.81) in serum samples, while in urine samples was (11.96±6.01). The results and comparisons indicate that radon concentrations depend on the variables on which this study was based. By comparing the radon concentrations for serum and urine with the age groups, the <em>p</em>-value was increased significantly statistically. Also, it was found that there is a positive and good correlation for radon concentrations between serum and urine. Therefore, it can be concluded radon concentrations were within the limits allowed globally, and thus, serum and urine were free from environmental pollution. Keywords: 222Rn concentrations; serum; urine; smokers; RAD-7 detector; Najaf governorate Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 18 - 27 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139138 Issue No:Vol. 17, No. 1 (2024)
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Authors:Abdulhussein A. Alkufi, Mohanad H. Oleiwi, Ali Abid Abojassim Pages: 28 - 48 Abstract: Real weighting functions needed for nuclear cross-section generation are problem dependent and should be calculated for each case study. It is an art to build an appropriate guess for within-group flux shape. However, it has been already proved that the shape of weighting spectrum is often enough to calculate the correct group constants. The main goal of the current investigation is to find the answer to the following question: How sensitive are cross-section, infinite multiplication factor and the nuclide concentrations to the applied different weighting functions? Here, the mentioned important neutronic parameters are evaluated versus burn-up for standard TMI1 pin cell problem. Different multi-group libraries are generated using various spectra. The resulted infinite multiplication factor, neutronic concentrations and nuclide concentration are estimated quite well for the benchmark pin cell. Negligible differences are seen for some of the parameters like thermal diffusion coefficient, fast production cross-section and infinite multiplication factor. Keywords: cross-sections; weighting spectra; pin cell; self-shielding Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 28 - 48 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139140 Issue No:Vol. 17, No. 1 (2024)
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Authors:Heni Susiati, Sunardi Sunardi, Mohammad Taufik, Muhammad Abdul Kholiq Pages: 49 - 65 Abstract: Site management of a Nuclear Power Plant (NPP) encompasses the entire site suitability planning process, considering physical and social aspects, community acceptance, nuclear waste management and decommissioning. This research constitutes a Systematic Literature Review (SLR) synthesising prior studies concerning NPP site management strategies. We employed five databases named Scopus, DOAJ, Euro PMC, EBSCO and ProQuest for 2014 to 2023. Among 1594 titles, 16 published articles were identified for meta-analysis using the PRISMA framework. The findings indicate the existence of prerequisites that must be satisfied before NPP siting, including environmental suitability, resilience against natural disasters and consideration of social aspects such as settlements. Public engagement in the siting process is crucial for effectively managing NPPs, contributing to attaining clean and sustainable energy goals. Furthermore, a specialised strategy is imperative for NPP management to ensure adherence to security and safety protocols while preventing adverse impacts on the surrounding environment and facilitating nuclear decommissioning. Despite challenges like nuclear uncertainty from political factors and radioactive waste concerns, NPP presents a viable energy option for mitigating global climate change. Keywords: energy management; green energy; nuclear Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 49 - 65 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139133 Issue No:Vol. 17, No. 1 (2024)
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Authors:Jean Pierre Ndayiragije, Zaki Su'ud, Abdul Waris Pages: 66 - 84 Abstract: One of the most essential technical challenges in fast reactor design is coolant selection. This paper investigates neutronic studies on a 400 MW thermal Modified CANDLE burnup scheme in a fast reactor using helium gas, lead-bismuth eutectic, and liquid sodium coolants. The core has been separated into ten regions with the equivalent volume in radial direction and recharging every ten years. Natural uranium was loaded in the first region, and after ten years, it was transported to the second region. These movements have taken place in all regions and fuel in tenth region got out of core. The neutronic features such as burnup level, integral conversion ratio, relative power density, flux level, infinite multiplication factor and effective multiplication factor were carried out. According to the results of the multiplication factor, liquid sodium attained criticality faster than helium gas and lead-bismuth eutectic coolants. This makes it to be the best coolant. Keywords: fast reactor; coolant; modified CANDLE; SRAC; JENDL 4.0; effective multiplication factor Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 66 - 84 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139137 Issue No:Vol. 17, No. 1 (2024)
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Authors:Khalid Nabaoui, Abdessamad Didi, Hamid Bounouira, Fouad Taous, Samira Mimount, Hamid Amsil, El Mehdi Alibrahmi, Chakir El Mahjoub, Mohammed Darouich, Hicham Jabri, Iliasse Aarab, Abdelouahab Badague, Abdeslem Rrhioua, Otmane Allaoui Pages: 85 - 97 Abstract: This article explores the consequences of neutron irradiation on the characteristics of polyethylene used as sample shuttles sent for prolonged irradiation (3 hours) in the core of the TRIGA Mark II reactor. The results reveal alterations in the mechanical, thermal and chemical properties of polyethylene following neutron irradiation. Conclusions drawn from two distinct approaches - infrared and X-ray imaging - underscore the importance of understanding the impacts of neutron irradiation on materials intended to be exposed to neutron fluxes. This understanding is crucial to ensuring the safety and durability of these materials. Keywords: neutron irradiation; polyethylene; shuttles; TRIGA Mark II; infrared; X-ray imaging; neutron fluxes Citation: International Journal of Nuclear Energy Science and Technology, Vol. 17, No. 1 (2024) pp. 85 - 97 PubDate: 2024-06-14T23:20:50-05:00 DOI: 10.1504/IJNEST.2024.139139 Issue No:Vol. 17, No. 1 (2024)
Hybrid journal (It can contain Open Access articles)
[439 journals]
