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Title: Shielding Benchmark Computational Analysis

Abstract

Over the past several decades, nuclear science has relied on experimental research to verify and validate information about shielding nuclear radiation for a variety of applications. These benchmarks are compared with results from computer code models and are useful for the development of more accurate cross-section libraries, computer code development of radiation transport modeling, and building accurate tests for miniature shielding mockups of new nuclear facilities. When documenting measurements, one must describe many parts of the experimental results to allow a complete computational analysis. Both old and new benchmark experiments, by any definition, must provide a sound basis for modeling more complex geometries required for quality assurance and cost savings in nuclear project development. Benchmarks may involve one or many materials and thicknesses, types of sources, and measurement techniques. In this paper the benchmark experiments of varying complexity are chosen to study the transport properties of some popular materials and thicknesses. These were analyzed using three-dimensional (3-D) models and continuous energy libraries of MCNP4B2, a Monte Carlo code developed at Los Alamos National Laboratory, New Mexico. A shielding benchmark library provided the experimental data and allowed a wide range of choices for source, geometry, and measurement data. The experimental datamore » had often been used in previous analyses by reputable groups such as the Cross Section Evaluation Working Group (CSEWG) and the Organization for Economic Cooperation and Development/Nuclear Energy Agency Nuclear Science Committee (OECD/NEANSC).« less

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (US)
Sponsoring Org.:
USDOE Office of Science (US)
OSTI Identifier:
771417
Report Number(s):
P00-107854
TRN: US0100513
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: ANS Radiation Protection and Shielding Topical Conference, Spokane, WA (US), 09/17/2000--09/21/2000; Other Information: PBD: 17 Sep 2000
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BENCHMARKS; RADIATION PROTECTION; SHIELDING

Citation Formats

Hunter, H.T., Slater, C.O., Holland, L.B., Tracz, G., Marshall, W.J., and Parsons, J.L. Shielding Benchmark Computational Analysis. United States: N. p., 2000. Web.
Hunter, H.T., Slater, C.O., Holland, L.B., Tracz, G., Marshall, W.J., & Parsons, J.L. Shielding Benchmark Computational Analysis. United States.
Hunter, H.T., Slater, C.O., Holland, L.B., Tracz, G., Marshall, W.J., and Parsons, J.L. Sun . "Shielding Benchmark Computational Analysis". United States. https://www.osti.gov/servlets/purl/771417.
@article{osti_771417,
title = {Shielding Benchmark Computational Analysis},
author = {Hunter, H.T. and Slater, C.O. and Holland, L.B. and Tracz, G. and Marshall, W.J. and Parsons, J.L.},
abstractNote = {Over the past several decades, nuclear science has relied on experimental research to verify and validate information about shielding nuclear radiation for a variety of applications. These benchmarks are compared with results from computer code models and are useful for the development of more accurate cross-section libraries, computer code development of radiation transport modeling, and building accurate tests for miniature shielding mockups of new nuclear facilities. When documenting measurements, one must describe many parts of the experimental results to allow a complete computational analysis. Both old and new benchmark experiments, by any definition, must provide a sound basis for modeling more complex geometries required for quality assurance and cost savings in nuclear project development. Benchmarks may involve one or many materials and thicknesses, types of sources, and measurement techniques. In this paper the benchmark experiments of varying complexity are chosen to study the transport properties of some popular materials and thicknesses. These were analyzed using three-dimensional (3-D) models and continuous energy libraries of MCNP4B2, a Monte Carlo code developed at Los Alamos National Laboratory, New Mexico. A shielding benchmark library provided the experimental data and allowed a wide range of choices for source, geometry, and measurement data. The experimental data had often been used in previous analyses by reputable groups such as the Cross Section Evaluation Working Group (CSEWG) and the Organization for Economic Cooperation and Development/Nuclear Energy Agency Nuclear Science Committee (OECD/NEANSC).},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {9}
}

Conference:
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