Published May 2017 | Version v1
Miscellaneous

Assessment of COBRA-SFS cycle4 with various single phase flow tests

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

COBRA-SFS (Coolant Boiling in Rod Arrays - Spent Fuel Storage) code has widely been used to analyze flow field and temperature profile in spent fuel storage canisters. The flow mechanism within spent fuel storage system is natural circulation driven by temperature difference. It is hard to find a validation work about COBRA-SFS's ability to predict flow field rather than temperature profile under natural circulation. The test cases used in this study are flow mixing test at CNEN 4x4 rod bundle, flow redistribution test at Westinghouse two 14x14 rod bundles, and low flow transient test at PNL 2x6 rod bundle. In the flow mixing test at CNEN 4x4 rod bundle, the flow velocity at the corner channel was under-predicted. In the low flow transient test at PNL 2x6 rod bundle, flow velocity at the cold channel became negative earlier than the measured and the temperature rise was over-predicted at that subchannel

Part of:
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2017

Additional details

Publishing Information

Publisher
KRS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2017
Imprint Pagination
420 p.
Journal Page Range
p. 137-138

Conference

Title
2017 Spring Meeting of Korean Radioactive Waste Society
Dates
24-26 May 2017
Place
Daejeon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49091848
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; CONTAINERS; FUEL ELEMENT CLUSTERS; SPENT FUEL STORAGE; SPENT FUELS; TEMPERATURE DEPENDENCE; VALIDATION; VELOCITY
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUEL ASSEMBLIES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; STORAGE; TESTING

Optional Information

Notes
5 refs, 3 figs