RELAP5/MOD2 implementation on various mainframes including the IBM and SX-2 supercomputer
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6942614
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.
- Research Organization:
- Texas A and M Univ., College Station (USA)
- OSTI ID:
- 6942614
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
Similar Records
Qualification of modifications of interfacial shear and wall heat transfer of RELAP5/MOD2/36. 02 during reflooding
Analysis of FLECHT and FLECHT-SEASET reflood tests with RELAP5/MOD2
Assessment of RELAP5/MOD2, Cycle 36.02, using NEPTUN reflooding experimental data
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6946733
Analysis of FLECHT and FLECHT-SEASET reflood tests with RELAP5/MOD2
Journal Article
·
Fri Aug 01 00:00:00 EDT 1986
· Nucl. Technol.; (United States)
·
OSTI ID:5348992
Assessment of RELAP5/MOD2, Cycle 36.02, using NEPTUN reflooding experimental data
Technical Report
·
Sat Aug 01 00:00:00 EDT 1992
·
OSTI ID:10176395
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
COMPUTER CODES
COMPUTERS
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FINITE DIFFERENCE METHOD
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
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ACCIDENTS
COMPUTER CODES
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ENERGY TRANSFER
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FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IBM COMPUTERS
ITERATIVE METHODS
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MECHANICS
NATIONAL ORGANIZATIONS
NEC COMPUTERS
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PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS