Published 1991 | Version v1
Report Restricted

Comparison of SCDAP/RELAP5/MOD3 to TRAC-PF1/MOD1 for timing analysis of PWR fuel pin failures

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
  • 2. Halliburton NUS, Idaho Falls, ID (United States)

Description

A comparison has been made of SCDAP/RELAP5/MOD3- and TRAC-PF1/MOD1- based calculations of the fuel pin failure timing (time from containment isolation signal to first fuel pin failure) in a loss-of-coolant accident (LOCA). The two codes were used to calculate the thermal-hydraulic boundary conditions for a complete, double-ended, offset-shear break of a cold leg in a Westinghouse 4-loop pressurized water reactor. Both calculations used the FRAPCON-2 code to calculate the steady-state fuel rod behavior and the FRAP-T6 code to calculate the transient fuel rod behavior. The analysis was performed for 16 combinations of fuel burnups and power peaking factors extending up to the Technical Specifications limits. While all calculations were made on a best-estimate basis, the SCDAP/RELAP5/MOD3 code has not yet been fully assessed for large-break LOCA analysis. The results indicate that SCDAP/RELAP5/MOD3 yields conservative fuel pin failure timing results in comparison to those generated using TRAC-PF1/MOD1. 7 refs., 5 figs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92003324; NTIS; INIS; US Govt. Printing Office Dep.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
15 p.
Report number
EGG-M--91370

Conference

Title
1991 RELAP5/TRAC-B international users seminar.
Dates
4-8 Nov 1991.
Place
Baton Rouge, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23031920
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; F CODES; FAILURES; FUEL CANS; FUEL ELEMENTS; FUEL PINS; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; S CODES; T CODES; TIME RESOLUTION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESOLUTION; THERMAL REACTORS; TIMING PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-9111124--3.