Published March 1992 | Version v1
Report Restricted

An assessment of TRAC-PF1/MOD1 using Strathclyde 1/10 scale model refill tests

Creators

  • 1. Central Electricity Research Labs., Leatherhead (United Kingdom)

Description

TRAC-PF1/MOD1 predictions of LOCA refill experiments carried out on a 1/10 scale model PWR vessel are presented. The predictions show that TRAC underpredicts bypass for the test cases considered. Comparison results are presented and discussed. Simple sensitivity analysis of the interfacial drag models used is presented in an effort to explain the poor performance of the code

Availability note (English)

MF available from INIS under the Report Number; OSTI as TI92010406; NTIS; INIS; GPO.

Files

Restricted

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Additional details

Publishing Information

Imprint Pagination
57 p.
Report number
NUREG/IA--0055

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23055028
Subject category
S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTER CALCULATIONS; DRAG; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; INTERFACES; LOSS OF COOLANT; PERFORMANCE; PWR TYPE REACTORS; REACTOR SAFETY; SCALE MODELS; SENSITIVITY ANALYSIS; T CODES; TEST FACILITIES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).