LOFT input dataset reference document for RELAP5 validation studies

Technical Report · Wed Apr 01 00:00:00 EST 1992

OSTI ID:10146274

Birchley, J C ^[1]

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1. AEA Technology, Winfrith (United Kingdom)

Analyses of LOFT experiment data are being carried out in order to validate the RELAP5 computer code for future application to PWR plant analysis. The MOD1 dataset was also used by CEGB Barnwood who subsequently converted the dataset to run with MOD2. The modifications included changes to the nodalisation to take advantage of the crossflow junction option at appropriate locations. Additional pipework representation was introduced for breaks in the intact (or active) loop. Further changes have been made by Winfrith following discussion of calculations performed by the CEGB and Winfrith. These concern the degree of noding in the steam generator, the fluid volume of the steam generator downcomer, and the location of the reactor vessel downcomer bypass path. This document describes the dataset contents relating to the volume, junction, and heat slab data for the intact loop, reactor pressure vessel, broken loop, steam generator secondary, and ECC system. Also described are the control system for steady state initialization, standard trip settings and boundary conditions.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; AEA Technology, Winfrith (United Kingdom)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10146274
• Report Number(s): NUREG/IA-0072; AEEW-R-2454; ON: TI92013943
• Resource Relation: Other Information: PBD: Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
PWR TYPE REACTORS
LOSS OF COOLANT
R CODES
VALIDATION
MODIFICATIONS
LOFT REACTOR
COMPUTER CALCULATIONS
STEAM GENERATORS
HEAT TRANSFER
HYDRAULICS
ECCS
REACTOR COOLING SYSTEMS
220900
210200
990200
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS