A simplified two step thermal analysis method for Wolsung (CANDU) spent fuel dry storage canister
Journal Article
·
· International Communications in Heat and Mass Transfer; (United States)
- Korean Advanced Inst. of Science and Technology, Taejon (Korea, Republic of)
A simplified two step thermal analysis method has been develop to evaluate (1) the mean temperature of the CANDU fuel bundles within a fuel basket in a given spent fuel dry storage canister by HEATING5 code with additional input data and heat transfer correlations in the step-1 analysis and (2) the maximum fuel rod temperature within a CANDU 37-element fuel bundle by MAXROT code developed here for step-2 analysis. In addition, the results of sample analysis is performed to examine the parametric effects of the site-specific ambient conditions on the maximum fuel temperature within a canister are presented. The comparison between the results of step-1 analysis and the mock-up test, in particular, is quite satisfactory. In essence, the two-step thermal analysis method proposed here is a code package that used the HEATING5 and MAXROT codes, respectively, for step-1 and step-2 calculations in series.
- OSTI ID:
- 6541931
- Journal Information:
- International Communications in Heat and Mass Transfer; (United States), Journal Name: International Communications in Heat and Mass Transfer; (United States) Vol. 20:2; ISSN 0735-1933; ISSN IHMTDL
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
CANDU TYPE REACTORS
CASKS
COMPUTER CALCULATIONS
CONTAINERS
ENERGY TRANSFER
HEAT SOURCES
HEAT TRANSFER
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
NATURAL URANIUM REACTORS
PHWR TYPE REACTORS
POWER REACTORS
PRESSURE TUBE REACTORS
REACTORS
SPENT FUEL CASKS
THERMAL ANALYSIS
THERMAL REACTORS
WOLSUNG-1 REACTOR
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
CANDU TYPE REACTORS
CASKS
COMPUTER CALCULATIONS
CONTAINERS
ENERGY TRANSFER
HEAT SOURCES
HEAT TRANSFER
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
NATURAL URANIUM REACTORS
PHWR TYPE REACTORS
POWER REACTORS
PRESSURE TUBE REACTORS
REACTORS
SPENT FUEL CASKS
THERMAL ANALYSIS
THERMAL REACTORS
WOLSUNG-1 REACTOR