Joint Study on Reactor Physics of Next Generation-Reactor Physics of Next Generation Light-Water Reactors

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委员会（CEA）和日本大学协会（JUA）签署的，加入了京都大学关键大会（KUCA）的联合使用计划。目前的研究和发展方向有：(1)共振自屏蔽的计算方法，(2)超铀元素核特性的实验技术和计算方法，(3)灵敏度系数的计算和灵敏度分析的计算，(4)多普勒效应的计算方法。(5)反应堆物理研究的实验技术主要通过每年在京都大学或CEA举行的日法联合研讨会或技术会议的讨论，在JUA和CEA的合作框架内进行。1999年，双方对协议进行了第二次修订，将合作期限延长至2004年。主题(1)主要通过基准计算，建立基于子群法的共振自屏蔽效应计算方法，考虑共振核素共振吸收截面间干扰效应的计算方法，以及评估共振自屏蔽的空间依赖性。对于主题(2)，在日本和法国进行了裂变或俘获反应速率测量等实验和分析，并在信息交换的基础上进行了超铀元素燃耗基准计算。在主题(3)中，为了评估日本和法国核数据库差异的影响，通过对空洞反应性系数和慢化剂温度系数的基准计算发现，研究了获得足够灵敏度系数的计算方法和灵敏度分析的方法。对于主题(4)，通过基准计算研究准确计算核燃料多普勒效应的方法，因为该效应在核反应堆瞬态现象中尤为重要。在主题(5)中，进行了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的信息交换，以便为下一代反应堆物理的发展升级技术。因此，信息交流不仅限于下一代轻水堆的研发领域，还包括加速器驱动的亚临界堆等。值得注意的是，JUA和CEA关于空隙系数的联合论文将发表在《原子核》杂志上。科学。Eng。第136卷，作为本合作研究的成果。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) joined to the joint use program of the Kyoto University Critical Assembly (KUCA). At present, the research and development on (1) the method of calculation for the resonance self-shielding, (2) the experimental technique and the computational method for the nuclear characteristics of the transuranic elements, (3) the calculation of sensitivity coefficients and that for the sensitivity analysis, (4) the method of calculation for the Doppler effect, and (5) the experimental techniques for the reactor physics study are mainly performing within the framework of the cooperation between JUA and CEA through discussion in the Japan-France joint seminar or technical meeting held every year at Kyoto University or CEA. The … More second revision of the agreement was concluded in 1999 to extend the cooperation till 2004.For the theme (1), the development of a computational method for the resonance self-shielding effect based on the subgroup method, a computational method considering the interference effect among resonance absorption cross sections of resonant nuclides, and an assessment of the spatial dependence of resonance self-shielding are performing mainly through the benchmark calculations. For the theme (2), experiments and analyses of such as the fission or capture reaction rate measurement in Japan and France are performing as well as the burnup benchmark calculation of the transuranic elements on the basis of the information exchange. For the theme (3), in order to assess the effect of difference in the nuclear data library between Japan and France which was found through the benchmark calculations on the void reactivity coefficient and the moderator temperature coefficient, a study is performing to develop a computational method to obtain the adequate sensitivity coefficient and the methodology of the sensitivity analysis. For the theme (4), the methodology to calculate accurately the Doppler effect of nuclear fuel was investigating through the benchmark calculation, since this effect is especially important in the transient phenomena of nuclear reactors. For the theme (5), the information exchange on the various experimental techniques including the reactor noise experiment, the neutron flux and power distribution measurement is performing in order to upgrade the technique for the development of reactor physics in the next generation. Therefore, the information exchange is not restricted only in the area of R&D for next generation light-water reactors, but it also includes such as the accelerator driven subcritical reactors. It should be noted here that the joint paper between JUA and CEA on the void coefficient will be published in Nucl. Sci. Eng. Vol. 136, as a fruit of the present cooprative study. Less