Published April 1977 | Version v1
Report Restricted

STRIKIN-II: a cylindrical geometry fuel rod heat transfer program

Creators

Description

This report details numerical improvements made to C-E's ECCS version of the STRIKIN-II code to stabilize the solution and average the output when the no return to nucleate boiling heat transfer logic is being applied. Sensitivity studies performed in order to determine the effects on peak clad temperature and peak local oxidation percentage are also documented in this report

Availability note (English)

MF available from INIS under the Report Number; C-E Power Systems, Windsor, CT.

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The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
37 p.
Report number
CENPD--135-P(Suppl.5)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8347110
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CE STANDARD REACTOR; COMPUTER CODES; CRITICAL HEAT FLUX; ECCS; FUEL CANS; HOT SPOTS; LOSS OF COOLANT; MATHEMATICAL MODELS; OXIDATION; PERFORMANCE; PWR TYPE REACTORS; S CODES; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; CHEMICAL REACTIONS; DISTRIBUTION; ENRICHED URANIUM REACTORS; HEAT FLUX; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS