Published October 2018 | Version v1
Miscellaneous

Assessment of Void Fraction Predictability of System Codes in Subchannel and Bundle geometry

  • 1. Incheon National University, Incheon (Korea, Republic of)

Description

This study aims to assess the void fraction predictability of three different system codes, TRACE V5.0 Patch 5, MARS-KS 1.4, and RELAP5/MOD3.3 Patch 5. The assessment has been conducted against the experimental data from OCED/NRC PSBT (PWR Subchannel and Bundle Test) benchmark. The test cases under steady-state conditions with subchannel and bundle geometries have been selected to the evaluation. The void fraction predictability of the system codes, TRACE, MARS-KS, and RELAP5, have been assessed against experimental results from OECD/NRC PSBT benchmark. The calculated results for single channel cases indicate that all the system codes systematically overpredict the void fraction in low void conditions, and the overprediction tendency could be also identified in bundle cases whereas in high void condition the prediction lies within 2σ. The statistical investigation confirms that TRACE results in higher prediction error compared to MARS-KS and RELAP5. The overprediction tendency is confirmed clearly for under 30% void fraction condition.

Part of:
Proceedings of the KNS 2018 Fall Meeting

Additional details

Identifiers

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2018 Fall Meeting
Imprint Pagination
vp.
Journal Page Range
[4 p.]

Conference

Title
2018 Fall Meeting of the KNS
Dates
24-26 Oct 2018
Place
Yeosu (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50060408
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
EXPERIMENTAL DATA; FORECASTING; GEOMETRY; PWR TYPE REACTORS; SUBCOOLED BOILING; T CODES; VOID FRACTION; VOIDS
Descriptors DEC
BOILING; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICS; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 7 figs, 5 tabs