Nuclear Analysis最新文献

Neutronic safety assessment of an in-core irradiation rig for NTD applications in the Tehran research reactor 德黑兰研究堆NTD堆芯辐照装置的中子安全性评价

Nuclear Analysis Pub Date : 2026-06-01 Epub Date: 2026-01-30 DOI: 10.1016/j.nucana.2026.100214

Mahdi Monshizadeh, Mojtaba Tajik

{"title":"Neutronic safety assessment of an in-core irradiation rig for NTD applications in the Tehran research reactor","authors":"Mahdi Monshizadeh, Mojtaba Tajik","doi":"10.1016/j.nucana.2026.100214","DOIUrl":"10.1016/j.nucana.2026.100214","url":null,"abstract":"<div><div>In-core irradiation devices should be introduced in research reactors through a neutronic safety margins assessment. The present study is directed at the evaluation of the effects that a proposed Neutron Transmutation Doping irradiation rig would impose on the Tehran Research Reactor. Changes in core reactivity and thermal neutron flux distribution and axial flux uniformity due to the addition of graphite reflector elements and thermal-absorbing flattening filters were quantified using MCNPX 2.6 simulations. The graphite structure increased excess reactivity by +579 pcm, while the stainless steel, Inconel, and nickel filters effectively countered such an increase and achieved lower than ±1.7% axial flux uniformities. There was no significant distortion introduced in the core spatial flux shape, and all neutronic performance measures remained within IAEA-proposed limit recommendations. These results suggest that the proposed irradiation system could be implemented in TRR without significantly compromising reactor safety, thereby forming a validated basis for future experimental implementation of silicon NTD at TRR.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 2","pages":"Article 100214"},"PeriodicalIF":0.0,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147387801","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Thermal analysis and simulation of key parameters in target design for laboratory fusion systems 实验室聚变系统靶设计中关键参数的热分析与仿真

Nuclear Analysis Pub Date : 2026-06-01 Epub Date: 2026-02-10 DOI: 10.1016/j.nucana.2026.100215

Maryam Ghapanvary , Fatemeh Bakhshoodeh Pour , Alireza aslezaeem

引用次数: 0

Radiological hazard assessment and statistical analysis of radionuclides in the soil samples of Raparin region, Iraq 伊拉克拉帕林地区土壤样品中放射性核素的放射性危害评价与统计分析

Nuclear Analysis Pub Date : 2026-06-01 Epub Date: 2026-02-10 DOI: 10.1016/j.nucana.2026.100216

Hiwa Mohammad Qadr

{"title":"Radiological hazard assessment and statistical analysis of radionuclides in the soil samples of Raparin region, Iraq","authors":"Hiwa Mohammad Qadr","doi":"10.1016/j.nucana.2026.100216","DOIUrl":"10.1016/j.nucana.2026.100216","url":null,"abstract":"<div><div>Soil samples from the Raparin region of Iraqi Kurdistan were analyzed to determine natural radionuclide concentrations and assess the associated radiological hazards. Monitoring indoor and outdoor radioactivity is essential for evaluating potential health risks and developing mitigation strategies. In this study, gamma-ray spectroscopy with a high-purity germanium detector (2.78 × 2.78 inches) was employed to measure activity concentrations of <sup>238</sup>U, <sup>232</sup>Th, and <sup>40</sup>K. The measured concentrations were 72.16±4.09, 85.94±5.09, and 324.58 ± 16.58 Bq kg<sup>−1</sup>, respectively. Based on these values, several hazard indices were calculated, including radium equivalent activity, absorbed dose rate, gamma activity index, external and internal hazard indices, annual effective dose, excess lifetime cancer risk, and organ-specific effective dose rates. The results were compared with international safety limits to evaluate potential risks. Statistical analyses, including skewness, kurtosis, and Pearson correlation coefficients, were applied to characterize radionuclide distributions and relationships. The study highlights the need for further assessment of exposure risks in regional soil samples.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 2","pages":"Article 100216"},"PeriodicalIF":0.0,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147387800","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Determination of gadolinium in leachate by PGNAA PGNAA法测定渗滤液中的钆

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-12-11 DOI: 10.1016/j.nucana.2025.100205

O.V. Chakilev, S.V. Kolesnikov, S.G. Rudakov

引用次数: 0

Quantitative analysis of MMRTG power decay due to thermal inventory loss 热库存损失导致MMRTG功率衰减的定量分析

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2026-03-10 DOI: 10.1016/j.nucana.2026.100218

Haoqian Qiu, Tailin Li, Yingzeng Zhang, Youhong Liu, Qingpei Xiang

{"title":"Quantitative analysis of MMRTG power decay due to thermal inventory loss","authors":"Haoqian Qiu, Tailin Li, Yingzeng Zhang, Youhong Liu, Qingpei Xiang","doi":"10.1016/j.nucana.2026.100218","DOIUrl":"10.1016/j.nucana.2026.100218","url":null,"abstract":"<div><div>The Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) experiences electrical power decline due to Pu-238 decay and thermoelectric (TE) degradation. In this work, the contribution of Pu-238 decay is isolated and quantified by modeling thermal inventory loss as the sole aging mechanism. A full-scale three-dimensional coupled thermal-electrical finite-element model of the MMRTG is constructed and evaluated over a 17-year operating period, with temperature-dependent thermoelectric material properties retained in each quasi-steady solution, but with no time-dependent aging or degradation of thermoelectric properties, contact resistance, or radiative properties. The results indicate that fuel decay alone reduces the electrical output from approximately 124 W<sub>e</sub> at beginning-of-life to ∼98.4 W<sub>e</sub> after 17 years, corresponding to a cumulative reduction of ∼20.6%. This behavior is equivalent to an effective compounded electrical decay rate of approximately 1.3-1.35%/yr, exceeding the commonly assumed 1.1%/yr decay-only approximation and leading to a ∼4% overprediction of end-of-life power in simplified models. Comparison of this decay-only reference with published Curiosity MMRTG flight telemetry enables a quantitative decomposition of total power loss. Over 17 years, approximately 45% (∼25 W<sub>e</sub>) of the cumulative loss is attributable to Pu-238 decay, while the remaining ∼55% (∼30 W<sub>e</sub>) appears as a lumped non-decay residual, interpreted here primarily as the consequence of thermoelectric aging together with other non-decay loss mechanisms and model–flight mismatch effects. The decay-only trajectory defined here provides a physically constrained reference for interpreting MMRTG performance data and separating unavoidable nuclear decay effects from thermoelectric aging.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100218"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"147448613","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

New arrangements of FAs at BNPP's reactor: PPF and burnup calculations 法国核动力集团反应堆中FAs的新安排：PPF和燃耗计算

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-11-26 DOI: 10.1016/j.nucana.2025.100204

Farhad Zolfagharpour, Zeinab Tayyari-Sadegh

{"title":"New arrangements of FAs at BNPP's reactor: PPF and burnup calculations","authors":"Farhad Zolfagharpour, Zeinab Tayyari-Sadegh","doi":"10.1016/j.nucana.2025.100204","DOIUrl":"10.1016/j.nucana.2025.100204","url":null,"abstract":"<div><div>In this work, the two assemblies named 16B36 and 36B20, and two arrangements named B and C, were introduced. The current arrangement of assemblies (named arrangement A) in the core of the BNPP reactor, was changed and the new assemblies were replaced, while the main characteristics of the core were maintained unchanged. The new arrangements and new assemblies were simulated in the MCNPX.2.6.0 code. For each arrangement, some parameters were calculated like: the effective multiplication factor, power peaking factor (PPF), energy deposition, average linear power density, maximum linear heat rate in hot rod, and the burnup after 300 operation days. According to the obtained results, arrangement C was suggested for use in BNPP at the first cycle of reactor operation, because in arrangement C, the burnup increases to about 3.3 GWd/MTU, the linear power density increases about 29 %, and the radial power distribution becomes significantly flattened, while the safety margin, including the maximum heat rate in hot rod, is maintained. The maximum heat rate in the hot rod was 35.95 kw/m which is below the allowed value (44.8 kw/m) reported in FSAR.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100204"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145738019","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Polyvinyl alcohol composites (PVA) with added Pb, Bi, and Sn: A study on radiation shielding and gamma ray attenuation 添加铅、铋和锡的聚乙烯醇复合材料（PVA）的辐射屏蔽和γ射线衰减研究

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-11-24 DOI: 10.1016/j.nucana.2025.100203

Ali K. Al-Muttairi , Norlaili A. Kabir

{"title":"Polyvinyl alcohol composites (PVA) with added Pb, Bi, and Sn: A study on radiation shielding and gamma ray attenuation","authors":"Ali K. Al-Muttairi , Norlaili A. Kabir","doi":"10.1016/j.nucana.2025.100203","DOIUrl":"10.1016/j.nucana.2025.100203","url":null,"abstract":"<div><div>Lead (Pb) is widely used for radiation shielding due to its high atomic number, density, affordability, and availability. However, its toxicity poses serious environmental and health risks. This study aims to evaluate the gamma-ray shielding performance of polyvinyl alcohol (PVA)-based shielding composites in the attenuation of <sup>60</sup>Co, <sup>137</sup>Cs, and <sup>241</sup>Am sources. A PVA-based shielding material incorporating Pb, Bi<sub>2</sub>O<sub>3</sub>, and Sn were evaluated for its radiation attenuation properties, using Pb as the benchmark standard for comparison of shielding effectiveness. PVA was selected for its hydrophilicity, ease of mixing, and light-weight property. A total of 18 shielding samples were fabricated, with six samples for each metal. The variables include metal percentages of 10 %, 20 %, and 30 %, as well as thicknesses of 0.6, 0.8, and 1.0 cm. Pb composites showed the highest attenuation among all samples, while Bi<sub>2</sub>O<sub>3</sub> and Sn composites also demonstrated strong shielding performance. The results showed that increasing the metal percentage per unit thickness has a much greater effect on shielding performance than simply increasing thickness. Increasing metal percentage at constant thickness significantly increases both linear and mass attenuation coefficients for all samples while reducing their HVL. At a constant thickness of 0.8 cm, increasing the metal composition from 10 % to 30 % results in a rise in the linear attenuation coefficient. For PVA/Pb, it increases from 1.75 cm<sup>−1</sup> to 2.7 cm<sup>−1</sup>, for PVA/Bi<sub>2</sub>O<sub>3</sub>, from 1.8 cm<sup>−1</sup> to 1.9 cm<sup>−1</sup>, and for PVA/Sn, from 1.3 cm<sup>−1</sup> to 1.5 cm<sup>−1</sup>. In summary, optimal shielding efficiency is primarily determined by the metal percentage per unit thickness, as photon attenuation depends more on the concentration of heavy atoms along the radiation path than on overall shielding thickness.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100203"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145685080","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Activity levels and radiological hazards of chemical fertilizers used for farm crops in Ondo city, Southwest, Nigeria 尼日利亚西南部翁多市用于农作物的化学肥料的活动水平和放射性危害

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-10-26 DOI: 10.1016/j.nucana.2025.100201

Lasun Tunde Ogundele , Muyiwa Micheal Orosun , Similoluwa Akiniran , Patrick Oluwagbemiga Ayeku

{"title":"Activity levels and radiological hazards of chemical fertilizers used for farm crops in Ondo city, Southwest, Nigeria","authors":"Lasun Tunde Ogundele , Muyiwa Micheal Orosun , Similoluwa Akiniran , Patrick Oluwagbemiga Ayeku","doi":"10.1016/j.nucana.2025.100201","DOIUrl":"10.1016/j.nucana.2025.100201","url":null,"abstract":"<div><div>Fertilizers contain several radioactive elements of the decay series of <sup>238</sup>U, <sup>226</sup>Ra and <sup>232</sup>Th and they can be a source of human exposure to gamma radiation when crops grown with fertilizers are consumed by human. The activity concentrations of <sup>238</sup>U, <sup>232</sup>Th and <sup>40</sup>K in three brands of fertilizers were measured using gamma-ray spectrometry and the radiological indices [Radium Equivalent activity (Ra<sub>eq</sub>), Absorbed Dose rate (DR), Annual Effective Dose rate (AED), External hazard (H<sub>ex</sub>), and Internal hazard (H<sub>in</sub>)] were estimated. The average activity concentrations of <sup>238</sup>U, <sup>232</sup>Th and <sup>40</sup>K were 4.98 ± 1.71, 12.35 ± 2.45 and 11.89.05 ± 288.91 Bqkg<sup>−1</sup>; 7.50 ± 1.84, 16.60 ± 3.32 and 2080.72 ± 251.25 Bqkg<sup>−1</sup> and 2.46 ± 0.68, 5.96 ± 1.24 and 306.82 ± 70.46 Bqkg<sup>−1</sup> for NPK 15-15-15, NPK 15-15-17 and Urea, respectively. The values of radiological indices were lower than the permissible limits stipulated by world average values except Ra<sub>eq</sub> and absorbed dose rate. Therefore, it can be concluded that no significant radiological health risk occurs. However, the presence of radionuclides in the fertilizers could be an exposure pathway that gamma radiation enters the food chain and threaten food production with deleterious health implications on the consumers of the such crops.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100201"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145618351","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Estimating the uranium content in blood samples of healthy and cancer-affected women in the city center of Al-Muthanna governorate, Iraq 估计伊拉克Al-Muthanna省市中心健康和癌症妇女血液样本中的铀含量

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-12-12 DOI: 10.1016/j.nucana.2025.100212

Tuqa Haider Al-Zaalimiu , Anees Ali Al-Hamzawi

{"title":"Estimating the uranium content in blood samples of healthy and cancer-affected women in the city center of Al-Muthanna governorate, Iraq","authors":"Tuqa Haider Al-Zaalimiu , Anees Ali Al-Hamzawi","doi":"10.1016/j.nucana.2025.100212","DOIUrl":"10.1016/j.nucana.2025.100212","url":null,"abstract":"<div><div>Uranium (U) is a heavy metal with chemical toxicity and radiological hazards. Chronic exposure, even at low concentrations, may contribute to serious health risks, including cancer. For this reason, it was necessary to measure the uranium content (UC) in blood samples of two groups of women (healthy and cancer patients) residing in the city center of Al-Muthanna Governorate. The Fission Track Analysis (FTA) technique with a CR-39 detector was applied to evaluate the UC in blood samples. Statistical comparisons between concentrations were performed using an independent <em>t</em>-test (p ≤ 0.05). The result illustrates that the UC in blood samples of the healthy women ranged from (0.74 ± 0.04 to 2.22 ± 0.04) with an average value equal to 1.14 ± 0.06 μg/l. In contrast, the UC for the cancer group ranged from (1.70 ± 0.04 to 4.22 ± 0.06) μg/l, with the mean value equal to 2.93 ± 0.05 μg/l. The findings revealed statistically significant differences (p < 0.001) in UC between the two groups, suggesting a correlation between the incidence of cancer in Iraqi women and elevated levels of UC in their blood. Preliminary observation showed higher UC among women working in the health sector (1.50 μg/l for healthy women and 3.59 μg/l for patients) compared to women in other occupations included in this study. Indicating a potential relationship between occupation type and increased UC. However, this association remains unconfirmed and requires further studies.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100212"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145790611","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Evaluating the health impact of indoor radon concentration in laboratory environments: a focus on lung cancer risk 评价实验室环境中室内氡浓度对健康的影响：以肺癌风险为重点

Nuclear Analysis Pub Date : 2026-03-01 Epub Date: 2025-12-17 DOI: 10.1016/j.nucana.2025.100213

Najeba Farhad Salih , Hiwa Mohammad Qadr

{"title":"Evaluating the health impact of indoor radon concentration in laboratory environments: a focus on lung cancer risk","authors":"Najeba Farhad Salih , Hiwa Mohammad Qadr","doi":"10.1016/j.nucana.2025.100213","DOIUrl":"10.1016/j.nucana.2025.100213","url":null,"abstract":"<div><div>This investigation assessed indoor radon concentrations across 11 laboratories using CR-39 solid-state nuclear track detectors to measure alpha particle emissions. Following exposure, detectors were chemically etched in 6.25 N sodium hydroxide solution at 70.0 ± 0.5 °C for 8 h to visualize alpha tracks, which were subsequently examined via optical microscopy. Measurements demonstrated considerable variability in radon levels between laboratories, even among those situated on identical floors. Radon concentrations ranged from 38.99 Bq m<sup>−3</sup> (Laboratory 11, third floor) to 61.66 Bq m<sup>−3</sup> (Laboratory 3, ground floor), yielding a mean value of 47.48 Bq m<sup>−3</sup>. Correspondingly, annual effective doses varied from 0.99 mSv y<sup>−1</sup> to 1.56 mSv y<sup>−1</sup>, with an average of 1.20 mSv y<sup>−1</sup>. These dose estimates remained substantially below ICRP recommended reference range of 3–10 mSv y<sup>−1</sup>. Excess lifetime cancer risk calculations showed values between 3.786 × 10<sup>−3</sup> (Laboratory 11) and 5.989 × 10<sup>−3</sup> (Laboratory 3). A statistically significant variation in radon concentration was also observed across different age groups (<em>P</em>-value <0.001). Critically, all measured concentrations fell below the UNSCEAR safety threshold of 200 Bq m<sup>−3</sup>, confirming that laboratory occupants face negligible health risks from radon exposure. The findings indicate no actionable radon hazards in the studied facilities.</div></div>","PeriodicalId":100965,"journal":{"name":"Nuclear Analysis","volume":"5 1","pages":"Article 100213"},"PeriodicalIF":0.0,"publicationDate":"2026-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145924684","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0