Published 1996 | Version v1
Book Metadata-only

STAR 3D nodal kinetics and thermal-hydraulic model for the Pennsylvania State TRIGA reactor

Creators

  • 1. Pennsylvania State Univ., Nuclear Engineering, University Park, PA (United States)

Description

A detailed three-dimensional (3D) time-dependent STAR nodal kinetics model coupled to a one-dimensional (1 D) thermal-hydraulics WIGL model has been developed to describe conservatively the peak power and pulse behavior of the Penn State University (PSU) Breazeale TRIGA reactor. This paper describes how the STAR model and its cross section data input was developed and benchmarked against actual TRIGA pulse experiments. Different core configurations (i.e., different core loading patterns, and with/without the TRIGA core next to the D20 tank) were used for several TRIGA pulse tests with different reactivity insertion worths (1.5$, 2.0$ , 2.5$). This paper shows that the STAR nodal kinetics code adequately simulates TRIGA pulses when group constants are generated from physics codes (i.e., WIMS-D4) that can accurately model the TRIGA uranium-zirconium-hydride fuel. (author)

Part of:
Simulation methods in nuclear engineering

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-47-X
Imprint Title
Simulation methods in nuclear engineering
Imprint Pagination
2 v.
Journal Page Range
(v.2) [16 p.]

Conference

Title
5. International conference on simulation methods in nuclear engineering
Dates
8-11 Sep 1996
Place
Montreal, PQ (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
33018530
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HYDRAULIC CONDUCTIVITY; LOSS OF COOLANT; NODAL EXPANSION METHOD; ONE-DIMENSIONAL CALCULATIONS; REACTOR CORES; REACTOR KINETICS; S CODES; THREE-DIMENSIONAL CALCULATIONS; TRIGA TYPE REACTORS; W CODES
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; KINETICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
14 refs., 5 tabs., 7 figs.