Joint Study on Reactor Physics for Light Water Reactors of Next Generation between Japanese University Association and Commissariat a l'Energie Atomique of France-

1993年4月，日本和法国开始进行一项合作研究，以促进下一代反应堆物理学的研究。该合作协议是由原子能能源委员会（CEA）和参与京都大学关键大会（KUCA）联合使用方案的日本大学协会（JUA）签订的。在本研究中，研究和开发了(1)包括多普勒效应在内的共振自屏蔽计算方法，(2)核燃料燃烧过程中微量锕系元素积累的评估，(3)通过实验结果分析对核数据和计算代码的评估。(4)通过每年在京都大学或CEA举行的日法联合研讨会的讨论，在JUA和CEA之间的合作框架内，集中开展了反应堆物理研究实验技术的进步。请注意，1999年双方对协议进行了第二次修订，将合作延长至2004年，目前正准备在2006年签署一项新协议。对于主题(1)，已经发展了几种考虑多普勒效应和共振核素共振吸收截面间干扰效应的谐振自屏蔽效应计算方法，主要通过与蒙特卡罗计算结果的比较来评估谐振自屏蔽中的空间效应。对于主题(2)，通过在辐照后实验基础上编制的基准问题，对累积超铀元素的CEA和JUA计算结果进行对比，检验燃耗计算的准确性。对于主题(3)，利用蒙特卡罗计算来评估日本和法国核数据库差异的影响，并正在进行研究，以开发获得足够灵敏度系数的计算方法和灵敏度分析的方法。在主题(4)中，将对包括反应堆噪声实验、中子通量和功率分布测量在内的各种实验技术进行信息交流和讨论，以提升建立下一代反应堆物理的实验技术。因此，信息交流不仅局限于下一代轻水反应堆的研发领域，还包括加速器驱动的亚临界反应堆（ADSR）等领域，京都大学反应堆研究所正在进行该领域的实验项目。少

A cooperative research between Japan and France was initiated to promote the study on the reactor physics of next generation in April 1993. The cooperation agreement was concluded between the Commissariat a l'Energie Atomique (CEA) and the Japanese University Association (JUA) involved in the joint use program of the Kyoto University Critical Assembly (KUCA). In the present study, the research and development on (1)the computational method of resonance self-shielding including Doppler effects, (2)the evaluation of the minor actinide accumulation in the course of nuclear fuel burnup, (3)the assessment of nuclear data and computational codes through analyses of experimental results, and (4)the advance in experimental techniques for the reactor physics study are intensively performing within the framework of the cooperation between JUA and CEA through discussion in the Japan-France joint seminar held every year at Kyoto University or CEA. Note that the second revision of the agreement was … More concluded in 1999 to extend the cooperation till 2004,and a new agreement is now preparing to be concluded in 2006.For the theme (1),several computational methods to calculate the resonance self-shielding effect in consideration of the Doppler effect and the interference effect among resonance absorption cross sections of resonant nuclides have been developed, and an assessment of the spatial effect in resonance self-shielding is performing mainly through the comparison with the results of Monte-Carlo calculations. For the theme (2),the accuracy of burnup calculation has been examined by comparing calculated results of CEA and JUA for accumulated transuranic elements through the benchmark problem prepared on the basis of post irradiation experiments. For the theme (3),the Monte-Carlo calculation has been utilized to assess the effect of difference in the nuclear data library between Japan and France, and a study is performing to develop a computational method to obtain the adequate sensitivity coefficient and the methodology for the sensitivity analysis. For the theme (4),the information exchange and discussion on the various experimental techniques including the reactor noise experiment, the neutron flux and power distribution measurement are ongoing in order to upgrade the experimental technique for establishing reactor physics for the development of next generation reactors. Therefore, the information exchange is not limited only in the R&D area for next generation light-water reactors, but it also includes the area such as the accelerator driven subcritical reactor (ADSR), for which an experimental project is underway at Research Reactor Institute, Kyoto University. Less