TRAC analysis support for the 2D/3D program. [PWR]
Conference
·
OSTI ID:6733510
The 2D/3D Program is a multinational (Germany, Japan, and the United States) experimental and analytical nuclear reactor safety research program having as its main purpose the investigation of multidimensional thermal-hydraulic behavior during the refill and reflood phases of loss-of-coolant accidents (LOCAs) in pressurized water reactors (PWRs). The German contribution to the program is the planned Upper Plenum Test Facility (UPTF), a full-scale facility with vessel, four loops, and steam-water core simulator. The Japanese are presently operating two large-scale test facilities as part of this program: the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The Los Alamos National Laboratory is the prime contractor to the NRC in the latter activity. The main analytical tool in this program is the Transient Reactor Analysis Code (TRAC), a best-estimate, multidimensional, non-equilibrium, thermal-hydraulics computer code developed for the NRC at Los Alamos. Through code predictions of experimental results and calculations of PWR transients, TRAC provides the analytic coupling between the facilities and is extending the results to predicting actual PWR behavior.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6733510
- Report Number(s):
- LA-UR-82-2834; CONF-821037-18; ON: DE83000615
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor safety issues resolved by the 2D/3D Program. International Agreement Report
TRAC analyses for CCTF and SCTF tests and UPTF design/operation. [Cylindrical Core Test Facility; Slab Core Test Facility; Upper Plenum Test Facility]
TRAC analyses for CCTF and SCTF tests and UPTF design/operation
Technical Report
·
Thu Jul 01 00:00:00 EDT 1993
·
OSTI ID:10177080
TRAC analyses for CCTF and SCTF tests and UPTF design/operation. [Cylindrical Core Test Facility; Slab Core Test Facility; Upper Plenum Test Facility]
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6411831
TRAC analyses for CCTF and SCTF tests and UPTF design/operation
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5444788
Related Subjects
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Nonboiling Water Cooled
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ACCIDENTS
COMPUTER CALCULATIONS
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WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS