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Title: Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE

Abstract

A three-dimensional (3-D) spatial kinetics capability within a thermal-hydraulics system code provides a more correct description of the core physics during reactor transients that involve significant variations in the neutron flux distribution. Coupled codes provide the ability to forecast safety margins in a best-estimate manner. The behavior of a reactor core and the feedback to the plant dynamics can be accurately simulated. For each time step, coupled codes are capable of resolving system interaction effects on neutronics feedback and are capable of describing local neutronics effects caused by the thermal hydraulics and neutronics coupling. With the improvements in computational technology, modeling complex reactor behaviors with coupled thermal hydraulics and spatial kinetics is feasible. Previously, reactor analysis codes were limited to either a detailed thermal-hydraulics model with simplified kinetics or multidimensional neutron kinetics with a simplified thermal-hydraulics model. The authors discuss the coupling of the Transient Reactor Analysis Code (TRAC)-PF1/MOD2, Version 5.4.25, with the NESTLE code.

Authors:
 [1]; ; ;  [2]
  1. Los Alamos National Lab., NM (United States)
  2. Pennsylvania State Univ., University Park, PA (United States)
Publication Date:
OSTI Identifier:
678157
Report Number(s):
CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009142
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999
Country of Publication:
United States
Language:
English
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 22 NUCLEAR REACTOR TECHNOLOGY; T CODES; N CODES; MODIFICATIONS; THREE-DIMENSIONAL CALCULATIONS; REACTOR KINETICS; REACTOR ACCIDENTS; HEAT TRANSFER; HYDRAULICS

Citation Formats

Knepper, P.L., Hochreiter, L.E., Ivanov, K.N., and Feltus, M.A. Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE. United States: N. p., 1999. Web.
Knepper, P.L., Hochreiter, L.E., Ivanov, K.N., & Feltus, M.A. Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE. United States.
Knepper, P.L., Hochreiter, L.E., Ivanov, K.N., and Feltus, M.A. Wed . "Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE". United States.
@article{osti_678157,
title = {Coupling of TRAC-PF1/MOD2, Version 5.4.25, with NESTLE},
author = {Knepper, P.L. and Hochreiter, L.E. and Ivanov, K.N. and Feltus, M.A.},
abstractNote = {A three-dimensional (3-D) spatial kinetics capability within a thermal-hydraulics system code provides a more correct description of the core physics during reactor transients that involve significant variations in the neutron flux distribution. Coupled codes provide the ability to forecast safety margins in a best-estimate manner. The behavior of a reactor core and the feedback to the plant dynamics can be accurately simulated. For each time step, coupled codes are capable of resolving system interaction effects on neutronics feedback and are capable of describing local neutronics effects caused by the thermal hydraulics and neutronics coupling. With the improvements in computational technology, modeling complex reactor behaviors with coupled thermal hydraulics and spatial kinetics is feasible. Previously, reactor analysis codes were limited to either a detailed thermal-hydraulics model with simplified kinetics or multidimensional neutron kinetics with a simplified thermal-hydraulics model. The authors discuss the coupling of the Transient Reactor Analysis Code (TRAC)-PF1/MOD2, Version 5.4.25, with the NESTLE code.},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 80,
place = {United States},
year = {1999},
month = {9}
}