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Title: Flux in a 1D-Reactor Cell by Response Matrix

Abstract

Legacy computational reactor physics software tools and protocols currently used for support of the Advanced Test Reactor (ATR) core fuel management and safety assurance, and to some extent, experiment management, are inconsistent with the state of modern nuclear engineering practice, and are difficult, if not impossible, to verify and validate (V&V) according to modern standards. Furthermore, the legacy staff knowledge required for effective application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. Thus in late 2009, the Idaho National Laboratory (INL) initiated a focused effort, the ATR Core Modeling Update Project, to address this situation through the introduction of modern high-fidelity transport theory based computational software and models to replace the legacy methods, with appropriate (V&V) protocols according to applicable national standards.

Authors:
 [1]; ORCiD logo [1];  [2]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Univ. of Arizona, Tucson, AZ (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1471675
Report Number(s):
INL/JOU-16-40410-Rev000
Journal ID: ISSN 0003-018X
Grant/Contract Number:  
AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 116; Journal Issue: 1; Journal ID: ISSN 0003-018X
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICS AND COMPUTING; verification; neutron transport; computational physics; analytic neutron flux

Citation Formats

Nigg, D.W., Crawford, S.S., and Ganapol, B. Flux in a 1D-Reactor Cell by Response Matrix. United States: N. p., 2017. Web.
Nigg, D.W., Crawford, S.S., & Ganapol, B. Flux in a 1D-Reactor Cell by Response Matrix. United States.
Nigg, D.W., Crawford, S.S., and Ganapol, B. Thu . "Flux in a 1D-Reactor Cell by Response Matrix". United States. https://www.osti.gov/servlets/purl/1471675.
@article{osti_1471675,
title = {Flux in a 1D-Reactor Cell by Response Matrix},
author = {Nigg, D.W. and Crawford, S.S. and Ganapol, B.},
abstractNote = {Legacy computational reactor physics software tools and protocols currently used for support of the Advanced Test Reactor (ATR) core fuel management and safety assurance, and to some extent, experiment management, are inconsistent with the state of modern nuclear engineering practice, and are difficult, if not impossible, to verify and validate (V&V) according to modern standards. Furthermore, the legacy staff knowledge required for effective application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. Thus in late 2009, the Idaho National Laboratory (INL) initiated a focused effort, the ATR Core Modeling Update Project, to address this situation through the introduction of modern high-fidelity transport theory based computational software and models to replace the legacy methods, with appropriate (V&V) protocols according to applicable national standards.},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = 1,
volume = 116,
place = {United States},
year = {2017},
month = {6}
}

Journal Article:
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