基于exfor的钚-242中子诱导裂变截面的同时评价

IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Science and Technology Pub Date : 2023-10-06 DOI:10.1080/00223131.2023.2267070
Riko Okuyama, Naohiko Otuka, Go Chiba, Osamu Iwamoto
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The newly evaluated 242Pu fission cross section was verified against the cross section measured in the 252Cf spontaneous fission neutron field and criticalities of small-sized LANL fast systems, and demonstrated better performance than the JENDL-4.0 cross section on the same level with the JENDL-5 cross section.KEYWORDS: Plutonium-242fissionsimultaneous evaluationJENDLEXFORDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementAntonio Jime´nez-Carrascosa and Oscar Cabellos (Universidad Polite´cnica de Madrid) per- formed criticality calculations by KENO to check if our criticality calculations are reasonable. We thank Melissa Denecke (IAEA) for careful reading of the manuscript. RO would like tothank the members of IAEA Nuclear Data Section for their hospitality during her internship. 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引用次数: 0

摘要

摘要在100 keV到200 MeV范围内对242Pu中子诱导裂变截面进行了计算。用最小二乘法对EXFOR库中242Pu和235U的裂变截面及其比值进行了回顾和分析。另外,通过将为JENDL-5评估开发的233,238U和239,240,241Pu裂变截面及其比值的实验数据库纳入其中,进行了额外的同步评估。我们的评价结果与JENDL-5评价结果在1 MeV以下的242Pu裂变截面接近,而在10 MeV以上的242Pu裂变截面存在系统差异。我们评估的截面在快速裂变中子谱峰区比JENDL-4.0的截面低(在1 MeV左右低约5%)。新计算的242Pu裂变截面与252Cf自发裂变中子场测量的截面和小型LANL快系统的临界值进行了验证,在与JENDL-5截面相同的水平上,其性能优于JENDL-4.0截面。作为对作者和研究人员的服务,我们提供此版本的已接受稿件(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。感谢antonio Jime ' nez-Carrascosa和Oscar Cabellos (universsidad Polite ' cnica de Madrid)使用KENO的临界计算来检查我们的临界计算是否合理。我们感谢梅丽莎·德内克(国际原子能机构)仔细阅读了手稿。总干事要感谢原子能机构核数据科成员在她实习期间的盛情款待。实习项目由日本文部科学省委托东京工业大学实施的“日本全球核人力资源开发大学网络核基础教育计划”资助。图1 242Pu/235U在1mev以下的裂变截面比来自于评估和本评估中使用的实验数据citation13, Citation48, Citation52, Citation53, Citation56, Citation57。图2242pu /235U在1mev以上的裂变截面比来自于评估和本评估中使用的实验数据citation13, Citation48, Citation52-57。图3242pu裂变截面来自于评估以及本评估中使用的实验截面citation12, Citation14, Citation15, Citation50, Citation51本评估中排除的三个数据集citation11, Citation16, Citation27也用灰色符号绘制。图4235u裂变截面来自评估以及本评估中使用的实验截面引文62 - 78。为便于阅读,省略实验数据点误差条。图5评价结果之间242Pu裂变截面的差异。图6目前评估的252Cf自发裂变中子谱平均截面的比率,评估数据库citation17, Citation19, Citation40-42和Mannhart的推荐citation45与AdamovCitation38测量的比率。ENDF / B-VIII。citation43和TENDL-2021Citation44库采用JENDL-4.0评价,未示出。图7 LANL小型快速系统(规格- met - fast -004-1, 2和3)临界度的C/E值由ACE-FRENDY-CBZ序列计算,JENDL-4.0库更新了当前的242Pu评估。本研究得到了国家教育、文化、体育、科学和技术部的支持。
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EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242
ABSTRACTThe 242Pu neutron-induced fission cross section was evaluated from 100 keV to 200 MeV. The experimental 242Pu and 235U fission cross sections and their ratios in the EXFOR library were reviewed and analysed by the least-squares method. Additional simultaneous evaluation was performed by including the experimental database of the 233,238U and 239,240,241Pu fission cross sections and their ratios developed for JENDL-5 evaluation. The 242Pu fission cross sec- tions from our evaluation and JENDL-5 evaluation are close to each other below 1 MeV while systematically differ from each other above 10 MeV. The cross section from our evaluation is systematically lower than the JENDL-4.0 cross section in the prompt fission neutron spectrum peak region (∼5% lower around 1 MeV). The newly evaluated 242Pu fission cross section was verified against the cross section measured in the 252Cf spontaneous fission neutron field and criticalities of small-sized LANL fast systems, and demonstrated better performance than the JENDL-4.0 cross section on the same level with the JENDL-5 cross section.KEYWORDS: Plutonium-242fissionsimultaneous evaluationJENDLEXFORDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementAntonio Jime´nez-Carrascosa and Oscar Cabellos (Universidad Polite´cnica de Madrid) per- formed criticality calculations by KENO to check if our criticality calculations are reasonable. We thank Melissa Denecke (IAEA) for careful reading of the manuscript. RO would like tothank the members of IAEA Nuclear Data Section for their hospitality during her internship. Her internship was financially supported by “Fundamental Nuclear Education Program by Japanese University Network for Global Nuclear Human Resource Development” entrusted to Tokyo Institute of Technology by Ministry of Education, Culture, Sports, Science and Technology (MEXT).Figure 1 242Pu/235U fission cross section ratios below 1 MeV from evaluations along with the experimental ones used in the present evaluationCitation13, Citation48, Citation52, Citation53, Citation56, Citation57.Display full sizeFigure 2 242Pu/235U fission cross section ratios above 1 MeV from evaluations along with the experimental ones used in the present evaluationCitation13, Citation48, Citation52–57.Display full sizeFigure 3 242Pu fission cross sections from evaluations along with the experimen- tal ones used in the present evaluationCitation12, Citation14, Citation15, Citation50, Citation51. Three datasets excluded from the present evaluationCitation11, Citation16, Citation27 are also plotted by grey symbols.Display full sizeFigure 4 235U fission cross sections from evaluations along with the experimental ones used in the present evaluationCitation62–78. Error bars of the experimental data points are omitted for readability.Display full sizeFigure 5 Difference in 242Pu fission cross sections between evaluations.Display full sizeFigure 6 Ratios of 252Cf spontaneous fission neutron spectrum averaged cross sections from present evaluation, evaluated data librariesCitation17, Citation19, Citation40–42 and Mannhart’s recommendationCitation45 to those measured by AdamovCitation38. The ENDF/B-VIII.0Citation43 and TENDL-2021Citation44 libraries adopt the JENDL-4.0 eval- uation and not shown.Display full sizeFigure 7 C/E values of the LANL small-sized fast system (SPEC-MET-FAST-004-1, 2 and 3) criticalities calculated by ACE-FRENDY-CBZ sequence with the JENDL-4.0 library updated with the present 242Pu evaluation.Display full sizeAdditional informationFundingThe work was supported by the Ministry of Education, Culture, Sports, Science and Technology .
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来源期刊
Journal of Nuclear Science and Technology
Journal of Nuclear Science and Technology 工程技术-核科学技术
CiteScore
2.40
自引率
16.70%
发文量
116
审稿时长
2.3 months
期刊介绍: The Journal of Nuclear Science and Technology (JNST) publishes internationally peer-reviewed papers that contribute to the exchange of research, ideas and developments in the field of nuclear science and technology, to contribute peaceful and sustainable development of the World. JNST ’s broad scope covers a wide range of topics within its subject category, including but are not limited to: General Issues related to Nuclear Power Utilization: Philosophy and Ethics, Justice and Policy, International Relation, Economical and Sociological Aspects, Environmental Aspects, Education, Documentation and Database, Nuclear Non-Proliferation, Safeguard Radiation, Accelerator and Beam Technologies: Nuclear Physics, Nuclear Reaction for Engineering, Nuclear Data Measurement and Evaluation, Integral Verification/Validation and Benchmark on Nuclear Data, Radiation Behaviors and Shielding, Radiation Physics, Radiation Detection and Measurement, Accelerator and Beam Technology, Synchrotron Radiation, Medical Reactor and Accelerator, Neutron Source, Neutron Technology Nuclear Reactor Physics: Reactor Physics Experiments, Reactor Neutronics Design and Evaluation, Reactor Analysis, Neutron Transport Calculation, Reactor Dynamics Experiment, Nuclear Criticality Safety, Fuel Burnup and Nuclear Transmutation, Reactor Instrumentation and Control, Human-Machine System: Reactor Instrumentation and Control System, Human Factor, Control Room and Operator Interface Design, Remote Control, Robotics, Image Processing Thermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.
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