Monte Carlo Analysis of Aqueous235U Critical Assemblies with ENDF/B-V Data
Author:
Affiliation:
1. Brookhaven National Laboratory Building 197D Upton, New York 11973
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE86-A17114
Reference20 articles.
1. National Nuclear Data Center, “Cross Section Evaluation Working Group Benchmark Specifications,” BNL-19302, ENDF-202, Brookhaven National Laboratory (1974).
2. J. J. ULLO and J. HARDY, Jr. “Analysis of Homogeneous U-233 and U-235 Critical Assemblies with ENDF/B-IV Data,” WAPD-TM-1299, Westinghouse Electric Corp., Bettis Atomic Power Laboratory (Oct. 1977).
3. N. R. CANDELORE, R. C. GAST, and L. A. ONDIS II, “RCP01 — A Monte Carlo Program for Solving Neutron and Photon Transport Problems in Three-Dimensional Geometry with Detailed Energy Description,” WAPD-TM-1267, Westinghouse Electric Corp., Bettis Atomic Power Laboratory (Aug. 1978).
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