Published 1999 | Version v1
Computer medium

Evaluation of fuel-temperature feedback mechanisms in TRAC-PF1/MOD2/NESTLE

  • 1. Los Alamos National Lab., Safeguards Systems Group, Los Alamos, NM (United States)

Description

Coupled spatial kinetics and thermal-hydraulics system codes provide a means to model transient nuclear reactor behavior more accurately. Transients marked by strong perturbations, both with thermal-hydraulics and neutronics, such as a control-rod ejection or a main steam-line break, are especially of interest. It is now feasible to model complex reactor behavior with a coupled thermal-hydraulics and spatial kinetics code that provides a means to forecast safety margins. Recently, the Transient Reactor Analysis Code (TRAC)-PF1/MOD2, Version 5.4.25, was coupled with the NESTLE code. This coupled code (TRAC-PF1/MOD2/NESTLE) is used to examine effective fuel-temperature models. The Electric Power Research Institute (EPRI) rod-ejection benchmark was analyzed to evaluate the influence of effective fuel temperature. The rod-ejection transient tests only the fuel-rod, heat-conduction coupling. The coolant thermal-hydraulic coupling is not tested because of the speed of the transient. The neutronics solution changes extremely rapidly, whereas the convective heat transfer at the fuel surface requires more time to influence the coolant temperature of the system. The need to model the response of the system coolant temperature is not crucial in this analysis. The influence of the effective fuel temperature is the key component of this study. Various models were examined using the coupled code to calculate effective fuel temperatures. The influence of different, effective fuel-temperature models on the coupled-code results is studied. Three effective fuel-temperature models are examined: (l) volume average effective fuel temperature, (2) the effective fuel-temperature model suggested by the Office of Economic Cooperation and Development (OECD) rod-ejection benchmark, and (3) the NESTLE effective fuel-temperature model. A discussion is provided describing the effective fuel-temperature models examined in TRAC-PF1/MOD2/NESTLE and the influence of effective fuel temperature in the code feedback mechanisms. (author)

Part of:
ICONE-7: Proceedings of the 7th international conference on nuclear engineering

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers
Imprint Place
Tokyo (Japan)
Imprint Title
ICONE-7: Proceedings of the 7th international conference on nuclear engineering
Imprint Pagination
4252 p.
Journal Page Range
[9 p.]

Conference

Title
7. international conference on nuclear engineering
Acronym
ICONE-7
Dates
19-23 Apr 1999
Place
Tokyo (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
31009075
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; EPRI; FEEDBACK; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; N CODES; POWER DISTRIBUTION; REACTOR KINETICS; ROD EJECTION ACCIDENTS; T CODES; TEMPERATURE DISTRIBUTION; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; KINETICS; REACTOR ACCIDENTS; REACTOR COMPONENTS

Optional Information

Notes
This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 07, ICONE-7461