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Title: Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations

Abstract

One of the high priority benchmarking activities for corroborating the Next Generation Nuclear Plant (NGNP) Project and Very High Temperature Reactor (VHTR) Program is evaluation of Japan's existing High Temperature Engineering Test Reactor (HTTR). The HTTR is a 30 MWt engineering test reactor utilizing graphite moderation, helium coolant, and prismatic TRISO fuel. A large amount of critical reactor physics data is available for validation efforts of High Temperature Gas-cooled Reactors (HTGRs). Previous international reactor physics benchmarking activities provided a collation of mixed results that inaccurately predicted actual experimental performance.1 Reevaluations were performed by the Japanese to reduce the discrepancy between actual and computationally-determined critical configurations.2-3 Current efforts at the Idaho National Laboratory (INL) involve development of reactor physics benchmark models in conjunction with the International Reactor Physics Experiment Evaluation Project (IRPhEP) for use with verification and validation methods in the VHTR Program. Annular cores demonstrate inherent safety characteristics that are of interest in developing future HTGRs.

Authors:
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1031736
Report Number(s):
INL/CON-09-16275
TRN: US1200170
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society: 2009 Winter Meeting,Washington, D.C.,11/15/2009,11/19/2009
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BENCHMARKS; CRITICALITY; ETR REACTOR; EVALUATION; GRAPHITE; HELIUM; INEEL; REACTOR PHYSICS; SAFETY; VALIDATION; VERIFICATION; Benchmark; Graphite Reactor; HTTR; IRPhEP; Prismatic Fuel; TRISO

Citation Formats

Bess, John D. Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations. United States: N. p., 2009. Web.
Bess, John D. Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations. United States.
Bess, John D. 2009. "Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations". United States. https://www.osti.gov/servlets/purl/1031736.
@article{osti_1031736,
title = {Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations},
author = {Bess, John D},
abstractNote = {One of the high priority benchmarking activities for corroborating the Next Generation Nuclear Plant (NGNP) Project and Very High Temperature Reactor (VHTR) Program is evaluation of Japan's existing High Temperature Engineering Test Reactor (HTTR). The HTTR is a 30 MWt engineering test reactor utilizing graphite moderation, helium coolant, and prismatic TRISO fuel. A large amount of critical reactor physics data is available for validation efforts of High Temperature Gas-cooled Reactors (HTGRs). Previous international reactor physics benchmarking activities provided a collation of mixed results that inaccurately predicted actual experimental performance.1 Reevaluations were performed by the Japanese to reduce the discrepancy between actual and computationally-determined critical configurations.2-3 Current efforts at the Idaho National Laboratory (INL) involve development of reactor physics benchmark models in conjunction with the International Reactor Physics Experiment Evaluation Project (IRPhEP) for use with verification and validation methods in the VHTR Program. Annular cores demonstrate inherent safety characteristics that are of interest in developing future HTGRs.},
doi = {},
url = {https://www.osti.gov/biblio/1031736}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Nov 01 00:00:00 EDT 2009},
month = {Sun Nov 01 00:00:00 EDT 2009}
}

Conference:
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