Study on Micro Reactor Physics for Improvement of Neutronics Calculation
改进中子学计算的微反应堆物理研究
基本信息
- 批准号:13480148
- 负责人:
- 金额:$ 6.34万
- 依托单位:
- 依托单位国家:日本
- 项目类别:Grant-in-Aid for Scientific Research (B)
- 财政年份:2001
- 资助国家:日本
- 起止时间:2001 至 2003
- 项目状态:已结题
- 来源:
- 关键词:
项目摘要
1)We have developed the theory for transient analysis with the consideration of Micro-reactor physics effect, and have developed the calculation code based on the developed theory. The current Coupling Collision probability method (CCCP method) is adopted in the developed theory because the CCCP method can strictly model the heterogeneity such as a pin cell structure in a fuel assembly and can treat the heterogeneity in calculating the effective cross sections: New CCCP method, which can treat the transient in time has been developed, because the conventional CCCP method does not consider the transient2)The analysis based on Micro-reactor physics shows that the angular distribution of neutron flux is greatly affected by the surrounding geometry and composition. Therefore, we considered the technique to measure the angular distribution of neutron flux in the core. The designed technique uses the optical fiber detector and Cd tube. The technique was applied to the measurement of the angular distribution in the core assembled in C-core tank at KUCA, and the technique was found to be effective to measure the angular distribution of neutron flux.3)The neutronics-thermodynamics coupling code has been developed to evaluate the effect of temperature distribution in fuel rods during the transient phenomena. The developed code was used to analyze the control rod drop accidents at the cold and hot stand-by states with the direct modeling of the heterogeneity of temperature distribution etc. in fuel rods. As the results, it is found that the analysis based on Micro-reactor physics is necessary and useful to consider the complex temperature distribution in fuel rods at a transient, and also the effective temperature model, which has a flat temperature distribution in fuel rods, bring the miscellaneous results because of the complex temperature, distribution.
1)我们已经在考虑微反应物物理效应的情况下开发了瞬时分析的理论,并根据开发的理论制定了计算代码。 The current Coupling Collision probability method (CCCP method) is adopted in the developed theory because the CCCP method can strictly model the heterogeneity such as a pin cell structure in a fuel assembly and can treat the heterogeneity in calculating the effective cross sections: New CCCP method, which can treat the transient in time has been developed, because the conventional CCCP method does not consider the transient2)The analysis based on Micro-reactor physics shows中子通量的角度分布受到周围几何和组成的极大影响。因此,我们考虑了测量核心中子通量的角度分布的技术。该设计的技术使用光纤检测器和CD管。该技术应用于库卡(Kuca)C核储罐中组装的核心分布的测量,发现该技术有效地测量了中子通量的角度分布。3)已开发了中性胞源 - 热力学偶联代码,以评估短暂势能过程中燃料棒中温度棒的效果。开发的代码用于分析燃油棒中温度分布等异质性的直接建模,在冷和热的状态下分析控制杆滴事故。作为结果,发现基于微反应物物理学的分析对于考虑瞬态燃油杆的复杂温度分布以及在燃料棒中具有固定温度分布的有效温度模型是必要且有用的,因此由于温度复杂而带来了杂项结果。
项目成果
期刊论文数量(104)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
Toshikazu TAKEDA, Yzuru HAMADA, Takanori KITADA: "3D Transport Theory Method Based on MOC for Analyzing Integral Data of Transmutation"Global2003. 1005-1010 (2003)
Toshikazu TAKEDA、Yzuru HAMADA、Takanori KITADA:“基于 MOC 分析嬗变积分数据的 3D 输运理论方法”Global2003。
- DOI:
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- 影响因子:0
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- 通讯作者:
Tsuyoshi AMA, Hideaki IKEDA, Shinya KOSAKA, Hideaki HYOUDOU, Toshikazu TAKEDA: "Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boling Water Reactor Cross"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 39
Tsuyoshi AMA、Hideaki IKEDA、Shinya KOSAKA、Hideaki HYOUDOU、Toshikazu TAKEDA:“环流慢化剂密度分布对博林水反应堆交叉燃料组件中子特性的影响”核科学与技术杂志。
- DOI:
- 发表时间:
- 期刊:
- 影响因子:0
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- 通讯作者:
Toshikazu TAKEDA: "Micro-Reactor Physics of MOX-Fueled Core"(印刷中).
Toshikazu TAKEDA:“MOX 燃料核心的微反应堆物理”(正在出版)。
- DOI:
- 发表时间:
- 期刊:
- 影响因子:0
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Toshikazu TAKEDA, Takanori KITADA: "Direction and Region Dependent Cross Sections for Use to MOX Fuel Analysis"(印刷中).
Toshikazu TAKEDA、Takanori KITADA:“用于 MOX 燃料分析的方向和区域相关横截面”(正在出版)。
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- 发表时间:
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- 影响因子:0
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Hideaki IKEDA, Toshikazu TAKEDA: "Development and Verification of an Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses"Journal of NUCLEAR SCIENCE and TECHNOLOGY. 38・7. 492-502 (2002)
Hideaki IKEDA、Toshikazu TAKEDA:“用于反应引发事件分析的有效空间中子动力学方法的开发和验证”核科学与技术杂志 38・7(2002)。
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- 影响因子:0
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TAKEDA Toshikazu其他文献
TAKEDA Toshikazu的其他文献
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{{ truncateString('TAKEDA Toshikazu', 18)}}的其他基金
A safety research on nuclear reactors based on the microscopic reactor physics
基于微观反应堆物理的核反应堆安全研究
- 批准号:
16360475 - 财政年份:2004
- 资助金额:
$ 6.34万 - 项目类别:
Grant-in-Aid for Scientific Research (B)
STUDY OF REACTIVITY COEFFICIENTS BASED ON REACTOR TRANSIENT ANALYSIS
基于反应堆瞬态分析的反应性系数研究
- 批准号:
63580180 - 财政年份:1988
- 资助金额:
$ 6.34万 - 项目类别:
Grant-in-Aid for General Scientific Research (C)
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