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Nuclear Data and Reactor Physics Activities in Indonesia

机译:印度尼西亚的核数据和反应堆物理活动

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The nuclear data and reactor physics activities in Indonesia, especially, in the National Atomic Energy Agency are presented. In the nuclear data field, the Agency is now taking the position of a user of the main nuclear data libraries such as JENDL and ENDF/B. These nuclear data libraries become the main sources for producing problem dependent cross section sets that are needed by cell calculation codes or transport codes for design, analysis and safety evalaution of research reactors. In the reactor physics field, besides utilising the existing core analysis codes obtained from bilateral and international co-operation, the Agency is putting much effort to self-develop Batan's codes for reactor physics calculations, in particular, for research reactor andf high temperature reactor design, analysis and fuel management. Under the collaboration with JAERI, Monte Carlo criticality calculations on the first criticality of RSG GAS (MPR-30) first core were done using JAERI continuous energy, vectorized Monte Carlo code, MVP, with JENDL-3.1 and JENDL_3.2 nuclear data libraries produced k_eff values with excellent agreement with experiment data, however, systematically, JENDL-3.2 library showed slightly higher k_eff values than JENDL-3.1 library.
机译:介绍了印度尼西亚特别是国家原子能机构在印度尼西亚的核数据和反应堆物理活动。在核数据领域,原子能机构现在正担任主要核数据库(如JENDL和ENDF / B)的用户的职务。这些核数据库成为产生与问题相关的横截面集的主要来源,而这些问题是研究计算堆的设计,分析和安全评估所需的电池计算代码或运输代码所需要的。在反应堆物理领域,原子能机构除了利用从双边和国际合作中获得的现有核心分析规则外,还付出了很多努力来自行开发巴丹的规则,以进行反应堆物理计算,特别是研究堆和高温堆设计,分析和燃料管理。在与JAERI的合作下,使用JAERI连续能量,矢量化的蒙特卡洛代码,MVP以及产生的JENDL-3.1和JENDL_3.2核数据库,对RSG GAS(MPR-30)第一核的第一临界度进行了蒙特卡洛临界度计算k_eff值与实验数据非常吻合,但是从系统上讲,JENDL-3.2库显示的k_eff值略高于JENDL-3.1库。

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