TRAC-PF1/MOD2-HWR analysis of flow in unheated prototypical SRS heavy-water reactor fuel assembly

Conference · Fri Jun 01 04:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6178346

Pasamehmetoglu, K; Birdsell, S; Fischer, S ^[1]

---

1. Los Alamos National Lab., NM (USA)

This paper summarizes the results of the authors effort comparing TRAC-PF1/MOD2-HWR predictions with Savannah River site (SRS) heavy-water reactor (HWR) prototype fuel-assembly data from unheated air/water experiments. This study was part of the benchmarking effort to evaluate and validate the multiple-assembly, full-plant model. The full-plant model is being developed by Los Alamos National Laboratory to study various aspects of the SRS plant operating conditions, including loss-of-coolant accident (LOCA) analysis using TRAC-PF1/MOD2-HWR. The paper discusses the experiments, the TRAC model, and the results of comparisons of TRAC calculations with the test data.

• OSTI ID: 6178346
• Report Number(s): CONF-900608--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCHMARKS
COMPUTER CODES
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LANL
LOSS OF COOLANT
MECHANICS
MODERATORS
MODIFICATIONS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
T CODES
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS