Analysis results from the Los Alamos 2D/3D program
- 1. Los Alamos National Lab., NM (USA)
Description
Los Alamos National Laboratory is a participant in the 2D/3D program. Activities conducted at Los Alamos National Laboratory in support of 2D/3D program goals include analysis support of facility design, construction, and operation; provision of boundary and initial conditions for test-facility operations based on analysis of pressurized water reactors; performance of pretest and post-test predictions and analyses; and use of experimental results to validate and assess the single- and multi-dimensional, nonequilibrium features in the Transient Reactor Analysis Code (TRAC). During fiscal year 1987, Los Alamos conducted analytical assessment activities using data from the Slab Core Test Facility, the Cylindrical Core Test Facility, and the Upper Plenum Test Facility. Finally, Los Alamos continued work to provide TRAC improvements. In this paper, Los Alamos activities during fiscal year 1987 are summarized; several significant accomplishments are described in more detail to illustrate the work activities at Los Alamos
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 4, Separate effects/experiments and analyses, Source term uncertainty analysis, Integral systems testing, 2D/3D research
- Journal Page Range
- p. 561-583.
- Report number
- NUREG/CP--0091-Vol.4
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20019275
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DATA; DATA PROCESSING; ECCS; FEDERAL REPUBLIC OF GERMANY; FLUID FLOW; FORECASTING; HEATING; HYDRAULICS; INTERNATIONAL COOPERATION; JAPAN; LASL; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; T CODES; TEMPERATURE DISTRIBUTION; TEST FACILITIES; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ASIA; COMPUTER CODES; COOPERATION; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; INFORMATION; LANL; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS