Web1 dic 2012 · The results for ENDF/B-VII.1 and JEFF-3.1.1 are more the 5000 pcm below the benchmark value, whereas the results for JENDL-4.0 are within the benchmark uncertainty range. There are two main possibilities why the performance of the libraries is so different for this benchmark case, whereas for the others the performance is similar. Webnuclear data library, JENDL-4.0, has been released,5) and its excellent performance for fission reactor applications has been reported.6) The present paper is also one of the JENDL-4.0 benchmark reports, and evaluates the perform-ance of JENDL-4.0 for eff prediction for fast neutron sys-tems. Experimental data of eff, which had been obtained at
今野 力 (Chikara Konno) - 論文 - researchmap
Webnuclear data library, JENDL-4.0, has been released,5) and its excellent performance for fission reactor applications has been reported.6) The present paper is also one of the … Web12 apr 2024 · The fuel temperature is 900K and moderator temperature is 600K. JENDL-4.0 is used . U-235 enrichment of matrix is 0.2wt%. Pu enrichment of each region is shown in Table 1. Isotopic ratio of Pu is shown in Table 2. The calculations of the modified OpenMOC are performed under the conditions shown in Table 3. register of deeds property search
(PDF) Neutron yield calculation of p-Li thick target by using PHITS ...
Web26 ott 2024 · JENDL project and related activities Abstract: The latest version of general-purpose file JENDL-4.0 was released in 2010 with improving fission product and minor actinide data as well as covariance data to meet needs of innovative reactors. Web摘要: 中子学积分实验是检验评价中子核数据库质量的一种重要手段,是核数据库建设工作的一项重要内容.国际上已开展了大量的积分实验,对数据库更新起到了重要作用,国内此方面的工作开展较少.铁是核装置的重要结构材料,其快中子截面数据的精确度对新型核装置设计具有重要意义.本论文采用板 ... Web19 ore fa · The database contains nuclear reaction data (neutron cross-sections and others) from main regional and national evaluated data libraries (ENDF/B-7.1, USA; JEFF-3.2, … probus club handbook