Multidimensional representation of German pressurized water reactor primary system in 200% break LOCA calculation
Creators
- 1. Gesellschaft fuer Reaktorsicherheit, Garching, West Germany
Description
The 3D-Vessel capability of TRAC-PF1/Mod1 (12.5) was used to study the influence of combined cold and hot leg ECC injection on flow and temperature distributions in the upper plenum as well as on the water break through from the upper plenum to the core region and finally on the core cooling. Two LOCA calculations have been performed. Based on a German Pressurized Water Reactor (GPWR) system a TRAC-PF1 input deck was designed to simulate the pressure vessel by a three-dimensional component of 15 axial levels, 4 radial rings and 8 azimuthal segments, the 4 loops separately by one-dimensional components including a fine noding of the steam generators and the main coolant pumps, and the complete ECC-injection system (cold and hot leg injection) consisting of high and low pressure pumps and accumulators
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 4, ECCS [Emergency Core Cooling Systems] rule revision, integral systems testing, separate effects/experiments and analyses, 2D/3D research
- Journal Page Range
- p. 499-521.
- Report number
- NUREG/CP--0082-Vol.4
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002214
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CODES; ECCS; EXPERIMENTAL DATA; FEDERAL REPUBLIC OF GERMANY; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; RUPTURES; STEAM GENERATORS; T CODES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTAINERS; COOLING SYSTEMS; DATA; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; FAILURES; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS