Published April 2010 | Version v1
Journal article

On the use of RELAP5-3D as a subchannel analysis code

  • 1. Nuclear Science and Engineering Department, Massachusetts Institute of Technology (MIT), 77 Massachusetts Ave., 02139 Cambridge, MA (United States)

Description

The capabilities of the RELAP5-3D code to perform subchannel analyses in sodium-cooled fuel assemblies were evaluated. The motivation was the desire to analyze fuel assemblies with traditional (solid pins) as well as non-traditional (e.g., annular pins with internal cooling, bottle-shape) geometries. Since no current subchannel codes can handle such fuel assembly designs, a new flexible RELAP5-based subchannel model was developed. It was shown that subchannel analysis of sodium-cooled fuel assemblies is indeed possible through the use of control variables in RELAP5. The subchannel model performance was then verified and validated in code-to-code and code-to-experiment analyses, respectively. First, the model was compared to the SUPERENERGY II code for solid fuel pins in a conventional hexagonal lattice. It was shown that the temperature predictions from the two codes agreed within 2% (<3.5 deg. C). Second, the model was applied to the Oak Ridge 19-pin test, and it was found that the measured outlet temperature distribution could be predicted with a maximum error of 8% (<7 deg. C). Furthermore, the use of semicircular ribs on the duct wall to flatten the temperature distribution in a traditional hexagonal assembly was explored by means of the newly developed RELAP5-3D subchannel model; the results are reported here as an example of the model capabilities.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2009.11.006

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2009.11.006;
PII
S0029-5493(09)00565-2;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
240
Journal Issue
4
Journal Page Range
p. 807-815
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41082879
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ANNULAR FUEL ELEMENTS; COOLING; DUCTS; ERRORS; FUEL ASSEMBLIES; FUEL PINS; R CODES; REACTOR LATTICES; SODIUM; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
Descriptors DEC
ALKALI METALS; COMPUTER CODES; ELEMENTS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; METALS; REACTOR COMPONENTS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.