Study on Reactor Physics of Next Generation Reactor by Japanese University Association -Joint Study with Commissariat a l'Energie Atomique of France -

日本和法国于1993年4月发起了一项合作研究，以促进下一代反应堆物理的研究。这项合作协议是由L能源协会(CEA)和日本大学协会(JUA)签署的，该协会加入了京都大学关键会议(KUCA)的联合使用计划。目前，(1)共振自屏蔽的计算方法，(2)超铀元素的核特性实验技术和计算方法，(3)灵敏度系数的计算方法和灵敏度分析方法，(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是在JUA和CEA合作的框架内，通过每年在京都大学…举行的日法联合研讨会或技术会议上的讨论而进行的更多城市或CEA。1999年对协议进行了第二次修订，将合作延长到2004年。对于主题(1)，主要通过基准计算开发了基于子群方法的共振自屏蔽效应的计算方法，考虑了共振核素的共振吸收截面之间的干扰效应的计算方法，以及对共振自屏蔽的空间相关性的评估。对于主题(2)，正在进行日本和法国的裂变或俘获反应速率测量等实验和分析，以及在信息交换的基础上进行超铀元素的燃耗基准计算。对于主题(3)，为了评估日本和法国核数据库中通过对空泡反应性系数和慢化剂温度系数的基准计算而发现的差异的影响，正在进行一项研究，以制定一种计算方法来获得适当的灵敏度系数和灵敏度分析的方法。对于主题(4)，通过基准计算探讨了准确计算核燃料多普勒效应的方法，因为这一效应在核反应堆的瞬变现象中尤为重要。对于主题(5)，正在进行各种实验技术的信息交流，包括反应堆噪声实验、中子通量和功率分布测量，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次临界反应堆等。这里应该指出的是，JUA和CEA之间关于空洞系数的联合论文将在《核不扩散条约》上发表。SCI。英语。第136卷，作为本次合作研究的成果。较少

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 method for 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 Univers … More ity or CEA. The 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 cooperative study. Less