ENDF/B-VII.0 Data Testing for Three Fast Critical Assemblies

Cullen, D E ; Blomquist, R N ; Brown, P N ; Dean, C J ; Dunn, M E ; Lee, Y ; Lent, E ; MacFarlane, R ; McKinley, S ; Plechaty, E F ; Sublet, J C

Lawrence Livermore National Laboratory

关键词: Testing;    Zero Power Reactors;    Nuclear Fuels;    22 General Studies Of Nuclear Reactors;    Computer Codes;   

DOI  :  10.2172/921339
RP-ID  :  UCRL-TR-233310
RP-ID  :  W-7405-ENG-48
RP-ID  :  921339

美国|英语

来源: UNT Digital Library

【 摘 要 】

In this report we consider three fast critical assemblies, each assembly is dominated by a different nuclear fuel: Godiva (U235), Jezebel (Pu239) and Jezebel23 (U233) [1]. We first show the improvement in results when using the new ENDF/B-VII.0 data [2], rather than the older, now frozen, ENDF/B-VI.8 data [3]. We do this using what we call a one code/ multiple library approach, where results from one code (MCNP) are compared using two different data libraries (ENDF/B-VII.0 and VI.8). Next we show that MCNP results are not specific to this one code by using what we call a one data library/multiple code approach; for this purpose we invited many codes to submit results using the ENDF/B-VII.0 data; the most detailed results presented in this report compare MCNP and TART. The bottom line is that we have shown that using the new ENDF/B-VII.0 data library with a variety of transport codes, for the first time we are able to reproduce the expected K-eff values for all three assemblies to within the quoted accuracy of the models, namely 1.0 +/- 0.001. This is a BIG improvement compared to the results obtained using the older ENDF/B-VI.8 data library. Another important result of this study is that we have demonstrated that currently there are many computer codes that can accurately use the new ENDF/B-VII.0 data.