Published October 2015 | Version v1
Miscellaneous

Assessment of TRACE Code for GE Level Swell Test to Review Industrial Code

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

Korea Institute of Nuclear Safety(KINS) has reviewed the industrial code for safety analysis of nuclear power plant, in which TRACE and MARS-KS codes are being used to support the understanding of specific phenomena and code prediction. For this aspect, the TRACE code was assessed for the GE Level Swell Experiment. General Electric (GE) performed a series of experiments to investigate thermal-hydraulic phenomena such as critical flow, void distribution, and liquid-vapor mixture swell during blowdown conditions. These GE Level swell experiments are frequently simulated to verify safety analysis codes as a separate effect test. TRACE code calculations with version 5.0 patch 4 for GE Level Swell experiment 1004-3 have been performed to assess the applicability of the TRACE code for verification of industrial code. An Assessment analysis of the TRACE version 5.0 patch 4 code was carried out for GE Level Swell experiments 1004-3 by comparison purpose with SPACE. Overall, TRACE predicted the pressure and axial void fractions at different times reasonably well for 1004-3 blowdown test, while SPACE tends to underestimate the pressure. It was also found that results of void fraction distribution should be compared at different time to discuss the accuracy of the SPACE code against this test

Part of:
Proceedings of the KNS 2015 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2015 Fall meeting of the KNS
Dates
28-30 Oct 2015
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47085359
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCURACY; FORECASTING; M CODES; NUCLEAR POWER PLANTS; S CODES; SAFETY ANALYSIS; T CODES; THERMAL HYDRAULICS; VERIFICATION; VOID FRACTION; VOIDS
Descriptors DEC
COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
2 refs, 5 figs, 1 tab