Published October 2002 | Version v1
Conference paper Metadata-only

Analysis of the OECD Peach Bottom turbine trip 2 transient benchmark with the coupled neutronic and thermal-hydraulics code TRAC-M/PARCS

Creators

  • 1. School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907-1290 (United States)
  • 2. US Nuclear Regulatory Commission (United States)
  • 3. Nuclear Engineering Program, The Pennsylvania State University, University Park, PA, 16802 (United States)

Description

An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. NRC coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady state and transient phases of the benchmark. (author)

Part of:
Proceedings of the PHYSOR 2002 International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
Imprint Pagination
12 p.

Conference

Title
International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
Acronym
Physor 2002
Dates
7-10 Oct 2002
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
55004290
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; BWR TYPE REACTORS; NEUTRON FLUX; PEACHES; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TRANSIENTS; TURBINES; TWO-PHASE FLOW
Descriptors DEC
ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; FLUID MECHANICS; FOOD; FRUITS; HYDRAULICS; MACHINERY; MECHANICS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; TURBOMACHINERY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
10 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)