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Investigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation system 为开发加速器驱动的核嬗变系统而对日本质子加速器研究综合体直线加速器中的随机束流行程进行的调查
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-20 DOI: 10.1080/00223131.2023.2296039
H. Takei
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引用次数: 0
The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding 循环弯曲载荷对气胀、破裂和氧化 Zircaloy-4 包层抗弯曲性的影响
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-17 DOI: 10.1080/00223131.2023.2293100
Feng Li, Takafumi Narukawa, Yutaka Udagawa
The seismic resistance of fuel cladding during the long-term core cooling after loss-of-coolant accidents (LOCAs) was investigated by performing cyclic four-point bending tests (4PBTs) of up to 100...
通过进行多达100次的循环四点弯曲试验(4PBT),研究了燃料包层在失去冷却剂事故(LOCA)后长期堆芯冷却期间的抗震性。
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引用次数: 0
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network 基于贝叶斯网络的核事故源项快速计算与预测技术研究
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-17 DOI: 10.1080/00223131.2023.2294193
Mingliang Xie, Yuqing Chen, Lei Yu, Wei Wei, Boyu Chen, Zhengquan Xie, Xueyan Hou
How to evaluate and predict potential source terms quickly and effectively is very important for emergency response. In this paper, the traditional forward analysis calculation based on determinist...
如何快速有效地评估和预测潜在的源条件对于应急响应非常重要。在本文中,传统的基于确定性的前瞻性分析计算方法已不再适用。
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引用次数: 0
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations 基于传热计算的轻水反应堆混合氧化物乏燃料直接处置概念
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-14 DOI: 10.1080/00223131.2023.2293106
Takumi Abe, Kenji Nishihara
Direct disposal concepts of mixed oxide spent fuel (MOXSF) consumed in light water reactors were investigated via heat transfer calculation. The temperature of the buffer material surrounding the w...
通过传热计算研究了轻水反应堆消耗的混合氧化物乏燃料(MOXSF)的直接处置概念。混合氧化物乏燃料周围缓冲材料的温度与...
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引用次数: 0
Status of the 226Ra nuclear data library and its impact on the production amount of 225Ac via the 226Ra (n,2n) reaction 226Ra 核资料库的现状及其对通过 226Ra (n,2n) 反应生成 225Ac 的影响
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-14 DOI: 10.1080/00223131.2023.2295018
Yuto Sasaki, Nobuyuki Iwamoto, Naoyuki Takaki, Shigetaka Maeda
225Ac is a promising alpha emitter for targeted alpha therapy. However, the current capability of 225Ac supply is limited to approximately 63 GBq/y, primarily relying on the natural source of 229Th...
225Ac 是一种很有前景的α发射体,可用于α靶向治疗。然而,目前 225Ac 的供应能力仅限于约 63 GBq/年,主要依赖于 229Th 的天然来源。
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引用次数: 0
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO2 and BWR-MOX fuels in the RUBUS program 对 RUBUS 计划中高燃烧压水堆-二氧化铀和生物质反应堆-MOX 燃料的实测核素清单进行蒙特卡洛燃烧分析
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-06 DOI: 10.1080/00223131.2023.2290068
Toru Yamamoto
To validate the nuclear data in JENDL-4.0 and obtain information to improve their accuracy, the analysis of the measured nuclide inventories of the high-burnup PWR UO2 and BWR MOX fuels in the REBU...
为了验证JENDL-4.0中的核数据并获得提高其准确性的信息,对REBU中高燃耗压水堆二氧化铀和双燃料反应堆MOX燃料的测量核素清单进行了分析。
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引用次数: 0
Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporation 考虑蒸发的裂变溶液沸腾临界事故功率分布分析
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-05 DOI: 10.1080/00223131.2023.2290711
Tomoaki Watanabe, Yuichi Yamane
The total fission energy released in a criticality accident involving fissile solution boiling tends to be high because the relatively high fission power continues during boiling. Simulating fissio...
裂变溶液沸腾的临界事故释放的总裂变能往往较高,因为在沸腾过程中仍有较高的裂变功率。模拟fissio……
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引用次数: 0
Mean-field dependence of fragment-production cross sections in heavy-ion induced reactions calculated by antisymmetrized molecular dynamics 反不对称分子动力学计算的重离子诱导反应中碎片生成截面的平均场依赖性
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-04 DOI: 10.1080/00223131.2023.2287102
Yuta Mukobara, Toshiya Sanami, Akira Ono, Tsunenori Inakura, Tastuya Katabuchi, Satoshi Chiba, Chikako Ishizuka
Dependence of the fragment production cross sections in heavy-ion induced reactions on employed mean-field models was investigated based on antisymmetrized molecular dynamics. For this purpose, fiv...
基于反不对称分子动力学,研究了重离子诱导反应中碎片产生截面与所采用的均场模型的关系。为此,研究人员采用了四...
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引用次数: 0
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents 核事故中地方政府灾害响应与决策支持系统数据库的建立研究
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-04 DOI: 10.1080/00223131.2023.2290713
Eunghyeon Kim, Minho Cha, Younwon Park, Minsang Ryu, Sooyeun Park, Kyeongil Ahn, Wonjo Kim, Haeyeol Gong
Radiological disasters have been recognized as a prominent societal catastrophe worldwide since the Fukushima nuclear accident in 2011. In order to cope with such disasters, efforts have been made ...
自2011年福岛核事故以来,放射性灾害被公认为世界范围内的重大社会灾难。为了应对这些灾难,人们已经做出了努力……
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引用次数: 0
Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition Model 基于马尔科夫状态转移模型的L1PRA不确定性分析方法的提出
IF 1.2 4区 工程技术 Q3 Energy Pub Date : 2023-12-04 DOI: 10.1080/00223131.2023.2287111
Masanobu Haruhara, Hitoshi Muta, Yasuki Ohtori, Shohei Yamagishi, Shota Terayama
In recent years, digital devices have been increasingly introduced into various control systems in nuclear power plants, and digital devices are even used in reactor protection systems (RPS). These...
近年来,数字装置越来越多地应用于核电站的各种控制系统中,甚至在反应堆保护系统(RPS)中也采用了数字装置。这些……
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引用次数: 0
期刊
Journal of Nuclear Science and Technology
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