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Title: A computer model for the transient analysis of compact research reactors with plate type fuel

Abstract

A coupled neutronics and core thermal-hydraulic performance model has been developed for the analysis of plate type U-Al fueled high-flux research reactor transients. The model includes point neutron kinetics, one-dimensional, non-homogeneous, equilibrium two-phase flow and beat transfer with provision for subcooled boiling, and spatially averaged one-dimensional beat conduction. The feedback from core regions other than the fuel elements is included by employing a lumped parameter approach. Partial differential equations are discretized in space and the combined equation set representing the model is converted to an initial value problem. A variable-order, variable-time-step time advancement scheme is used to solve these ordinary differential equations. The model is verified through comparisons with two other computer code results and partially validated against SPERT-II tests. It is also used to analyze a series of HFIR reactivity transients.

Authors:
 [1];  [2]
  1. Argonne National Lab., IL (United States)
  2. Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering
Publication Date:
Research Org.:
Argonne National Lab., IL (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10131029
Report Number(s):
ANL/RA/CP-79957; CONF-940402-12
ON: DE94007675
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; RESEARCH REACTORS; FUEL PLATES; TRANSIENTS; COMPUTER CODES; HFIR REACTOR; ATR REACTOR; HFBR REACTOR; MATHEMATICAL MODELS; HEAT TRANSFER; HYDRAULICS; REACTOR PHYSICS; REACTOR SAFETY; 220900; 220600; 220100; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; THEORY AND CALCULATION

Citation Formats

Sofu, T., and Dodds, H.L. A computer model for the transient analysis of compact research reactors with plate type fuel. United States: N. p., 1994. Web.
Sofu, T., & Dodds, H.L. A computer model for the transient analysis of compact research reactors with plate type fuel. United States.
Sofu, T., and Dodds, H.L. Tue . "A computer model for the transient analysis of compact research reactors with plate type fuel". United States. https://www.osti.gov/servlets/purl/10131029.
@article{osti_10131029,
title = {A computer model for the transient analysis of compact research reactors with plate type fuel},
author = {Sofu, T. and Dodds, H.L.},
abstractNote = {A coupled neutronics and core thermal-hydraulic performance model has been developed for the analysis of plate type U-Al fueled high-flux research reactor transients. The model includes point neutron kinetics, one-dimensional, non-homogeneous, equilibrium two-phase flow and beat transfer with provision for subcooled boiling, and spatially averaged one-dimensional beat conduction. The feedback from core regions other than the fuel elements is included by employing a lumped parameter approach. Partial differential equations are discretized in space and the combined equation set representing the model is converted to an initial value problem. A variable-order, variable-time-step time advancement scheme is used to solve these ordinary differential equations. The model is verified through comparisons with two other computer code results and partially validated against SPERT-II tests. It is also used to analyze a series of HFIR reactivity transients.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {3}
}

Conference:
Other availability
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