Assessment of the RELAP4/MOD6 thermal-hydraulic transient code for PWR experimental applications. Volume 1. Assessment analysis

Technical Report · Sun Jan 01 04:00:00 EST 1978

OSTI ID:6489953

The RELAP4/MOD6 computer code was recently released to the public by the Nuclear Regulatory Commission for use in reactor transient thermal-hydraulic analysis. The code has a unique new capability for calculation of both the blowdown and reflood portions of a postulated pressurized water reactor loss-of-coolant accident. Assessment of this code after its release represents the quality-evaluation phase of the code development program. A principal assessment objective is to provide tested and evaluated codes usable in the analysis of hypothesized LWR (light water reactor) accidents. This objective has been met through comparison and evaluation of code calculations with results of thermal-hydraulic experiments.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• OSTI ID: 6489953
• Report Number(s): CAAP-TR-78-035(Vol.)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS