Published 1991 | Version v1
Report Restricted

Assessment of TRAC-PF1/MOD3 Mark-22 assembly model using SRL ''A'' tank single-assembly flow experiments

Creators

Description

This paper summarizes the results of an assessment of our TRAC-PF1/MOD3 Mark-22 prototype fuel assembly model against single-assembly data obtained from the ''A'' Tank single-assembly tests that were performed at the Savannah River Laboratory. We felt the data characterize prototypic assembly behavior over a range of air-water flow conditions of interest for loss-of-coolant accident (LOCA) calculations. This study was part of a benchmarking effort performed to evaluate and validate a multiple-assembly, full-plant model that is being developed by Los Alamos National Laboratory to study various aspects of the Savannah River plant operating conditions, including LOCA transients, using TRAC-PF1/MOD3 Version 1.10. The results of this benchmarking effort demonstrate that TRAC-PF1/MOD3 is capable pf calculating plenum conditions and assembly flows during conditions thought to be typical of the Emergency Cooling System (ECS) phase of a LOCA. 10 refs., 12 fig

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE91009945; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
26 p.
Report number
LA-UR--91-826

Conference

Title
International topical meeting on safety of thermal reactors.
Dates
21-25 Jul 1991.
Place
Portland, OR (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22085830
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENCHMARKS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; COOLANTS; EXPERIMENTAL DATA; FLOW MODELS; FLUID FLOW; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRODUCTION REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; TANKS; TEST FACILITIES; TEST REACTORS; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DATA; ENERGY TRANSFER; INFORMATION; MATHEMATICAL MODELS; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-36
Funding organization
USDOE, Washington, DC (USA).
Secondary number(s)
CONF-910714--4.