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Nuclear data evaluation and group constant generation for reactor analysis

Abstract

Data testing of ENDF/B-VI.2 was performed and ACE-format continuous point-wise cross section library from ENDF/B-VI.2 for MCNP was validated through CSEWG benchmark and power plant mockup experiments. The calculated k-effective of ORNL-1, -2, -3, -4 and -10 with ENDF/B-VI are low by about 0.5% but those of L-7, -8, -9, -10 and -11 show good agreement with experiments. Overall results for uranium core with ENDF/B-VI is low in critically than with ENDF/B-V. The calculated results with ENDF/B-VI for PNL-6 {approx} 12 of plutonium core and PNL-30 {approx} 35 of mixed oxide core show good agreement with the experiments. The results of critically calculation for fast core benchmark do not show large difference between ENDF/B-VI and -V. But the calculated results of reaction rate ratio with ENDF/B-VI are improved, compared with ENDF/B-V. The calculated power distribution for VENUS PWR mockup core and typical BWR core of GE with both of ENDF/B-VI and -V agree well with measured values. From the above results, newly generated MCNP library from ENDF/B-VI is useful for nuclear and shielding design and analysis. 5 figs, 13 tabs, 11 refs. (Author).
Authors:
Kim, Jung Doh; Kil, Chung Sub [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Dec 01, 1994
Product Type:
Technical Report
Report Number:
KAERI-RR-1434/94
Reference Number:
SCA: 990301; PA: AIX-27:016737; EDB-96:042993; NTS-96:014139; SN: 96001546664
Resource Relation:
Other Information: PBD: Dec 1994
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; REACTOR CORES; GROUP CONSTANTS; NUCLEAR DATA COLLECTIONS; BENCHMARKS; COMPUTER CODES; FAST NEUTRONS; THERMAL NEUTRONS
OSTI ID:
187196
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96614932; TRN: KR9500127016737
Availability:
INIS; OSTI as DE96614932
Submitting Site:
KRN
Size:
60 p.
Announcement Date:

Citation Formats

Kim, Jung Doh, and Kil, Chung Sub. Nuclear data evaluation and group constant generation for reactor analysis. Korea, Republic of: N. p., 1994. Web.
Kim, Jung Doh, & Kil, Chung Sub. Nuclear data evaluation and group constant generation for reactor analysis. Korea, Republic of.
Kim, Jung Doh, and Kil, Chung Sub. 1994. "Nuclear data evaluation and group constant generation for reactor analysis." Korea, Republic of.
@misc{etde_187196,
title = {Nuclear data evaluation and group constant generation for reactor analysis}
author = {Kim, Jung Doh, and Kil, Chung Sub}
abstractNote = {Data testing of ENDF/B-VI.2 was performed and ACE-format continuous point-wise cross section library from ENDF/B-VI.2 for MCNP was validated through CSEWG benchmark and power plant mockup experiments. The calculated k-effective of ORNL-1, -2, -3, -4 and -10 with ENDF/B-VI are low by about 0.5% but those of L-7, -8, -9, -10 and -11 show good agreement with experiments. Overall results for uranium core with ENDF/B-VI is low in critically than with ENDF/B-V. The calculated results with ENDF/B-VI for PNL-6 {approx} 12 of plutonium core and PNL-30 {approx} 35 of mixed oxide core show good agreement with the experiments. The results of critically calculation for fast core benchmark do not show large difference between ENDF/B-VI and -V. But the calculated results of reaction rate ratio with ENDF/B-VI are improved, compared with ENDF/B-V. The calculated power distribution for VENUS PWR mockup core and typical BWR core of GE with both of ENDF/B-VI and -V agree well with measured values. From the above results, newly generated MCNP library from ENDF/B-VI is useful for nuclear and shielding design and analysis. 5 figs, 13 tabs, 11 refs. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Dec}
}