RELAP5/MOD2 implementation on various mainframes including the IBM and SX-2 supercomputer
Description
The RELAP5/MOD2 (cycle 36.04) code is a one-dimensional, two-fluid, nonequilibrium, nonhomogeneous transient analysis code designed to simulate operational and accident scenarios in pressurized water reactors (PWRs). System models are solved using a semi-implicit finite difference method. The code was developed at EG and G in Idaho Falls under sponsorship of the US Nuclear Regulatory Commission (NRC). The major enhancement from RELAP5/MOD1 is the use of a six-equation, two-fluid nonequilibrium and nonhomogeneous model. Other improvements include the addition of a noncondensible gas component and the revision and addition of drag formulation, wall friction, and wall heat transfer. Several test cases were run to benchmark the IBM and SX-2 installations against the CDC computer and the CRAY-2 and CRAY/XMP. These included the Edward's pipe blow-down and two separate reflood cases developed to simulate the FLECHT-SEASET reflood test 31504 and a postcritical heat flux (CHF) test performed at Lehigh University
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 55
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 709-710
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20003859
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERS; FINITE DIFFERENCE METHOD; HEAT TRANSFER; HYDRAULICS; IBM COMPUTERS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; TWO-PHASE FLOW; US NRC
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; ITERATIVE METHODS; NATIONAL ORGANIZATIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8711195--.