Assessment of TRAC-PF1/MOD1 version 14. 3 using separate effects critical flow and blowdown experiments

Technical Report · Mon Jan 01 00:00:00 EST 1990

OSTI ID:7175189

Spindler, B; Pellissier, M ^[1]

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1. CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France)

Independent assessment of the TRAC code was conducted at the Centre d'Etudes Nucleaires de Grenoble of the Commissariate a l'Energie Atomique (France) in the frame of the ICAP. This report presents the results of the assessment of TRAC-PF1/MOD1 version 14.3 using critical flow steady state tests (MOBY-DICK, SUPER-MOBY-DICK), and blowdown tests (CANON, SUPER-CANON, VERTICAL-CANON, MARVIKEN, OMEGA-TUBE, OMEGA-BUNDLE). This document, Volume 1, presents the text and tables from this assessment.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France)
• Sponsoring Organization: USNRC
• OSTI ID: 7175189
• Report Number(s): NUREG/IA-0023-Vol.1; ON: TI90010754; TRN: 90-016229
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BLOWDOWN
T CODES
CRITICAL FLOW
NUCLEAR POWER PLANTS
REACTOR COOLING SYSTEMS
EVALUATION
EXPERIMENTAL DATA
FLOW RATE
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
REACTOR SAFETY
STEADY-STATE CONDITIONS
VOID FRACTION
COMPUTER CODES
COOLING SYSTEMS
COOPERATION
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
INFORMATION
MECHANICS
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
REACTOR COMPONENTS
SAFETY
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
990200 - Mathematics & Computers