VIPRE-01: a thermal-hydraulic analysis code for reactor cores. Volume 2. User's manual. [PWR; BWR]

Technical Report · Fri Apr 01 00:00:00 EST 1983

OSTI ID:6025503

Cuta, J M; Koontz, A S; Stewart, C W; Montgomery, S D

VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear energy reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 2: User's Manual) describes the input requirements of VIPRE and its auxiliary programs, SPECSET, ASP and DECCON, and lists the input instructions for each code.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6025503
• Report Number(s): EPRI-NP-2511-CCM-Vol.2; ON: DE83013095
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR CORES
COMPUTER CODES
V CODES
PWR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
DEPARTURE NUCLEATE BOILING
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
TEMPERATURE DISTRIBUTION
THERMAL STRESSES
ACCIDENTS
BOILING
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
NUCLEATE BOILING
OPERATION
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled