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Title: Validation of Improved 3D ATR Model

Abstract

A full-core Monte Carlo based 3D model of the Advanced Test Reactor (ATR) was previously developed. An improved 3D model has been developed by the International Criticality Safety Benchmark Evaluation Project (ICSBEP) to eliminate homogeneity of fuel plates of the old model, incorporate core changes into the new model, and to validate against a newer, more complicated core configuration. This new 3D model adds capability for fuel loading design and azimuthal power peaking studies of the ATR fuel elements.

Authors:
 [1];  [1]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI Identifier:
911618
Report Number(s):
INL/CON-05-00322
Journal ID: ISSN 0003-018X; TRN: US0800045
DOE Contract Number:  
AC07-99ID-13727
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 03; Journal Issue: 1; Conference: ANS 2005 Winter Meeting, Washington, DC (United States), 13-17 Nov 2005; Related Information: https://www.ans.org/pubs/transactions/volume-93/; Journal ID: ISSN 0003-018X
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 97 MATHEMATICS AND COMPUTING; BENCHMARKS; CONFIGURATION; CRITICALITY; DESIGN; EVALUATION; FUEL ELEMENTS; FUEL PLATES; SAFETY; TEST REACTORS; VALIDATION; Nuclear Criticality Safety Program (NCSP); Advanced Test Reactor (ATR); Fuel Loading Design; Azimuthal Power Peaking Studies; International Criticality Safety Benchmark Evaluation Project (ICSBEP); Monte Carlo; Fuel Plates

Citation Formats

Kim, Soon S., and Schnitzler, Bruce G. Validation of Improved 3D ATR Model. United States: N. p., 2005. Web.
Kim, Soon S., & Schnitzler, Bruce G. Validation of Improved 3D ATR Model. United States.
Kim, Soon S., and Schnitzler, Bruce G. 2005. "Validation of Improved 3D ATR Model". United States. https://www.osti.gov/servlets/purl/911618.
@article{osti_911618,
title = {Validation of Improved 3D ATR Model},
author = {Kim, Soon S. and Schnitzler, Bruce G.},
abstractNote = {A full-core Monte Carlo based 3D model of the Advanced Test Reactor (ATR) was previously developed. An improved 3D model has been developed by the International Criticality Safety Benchmark Evaluation Project (ICSBEP) to eliminate homogeneity of fuel plates of the old model, incorporate core changes into the new model, and to validate against a newer, more complicated core configuration. This new 3D model adds capability for fuel loading design and azimuthal power peaking studies of the ATR fuel elements.},
doi = {},
url = {https://www.osti.gov/biblio/911618}, journal = {Transactions of the American Nuclear Society},
issn = {0003-018X},
number = 1,
volume = 03,
place = {United States},
year = {Thu Nov 17 00:00:00 EST 2005},
month = {Thu Nov 17 00:00:00 EST 2005}
}

Conference:
Other availability
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