Evaluation model calculations with the water reactor analysis package (WRAP-EM)
Journal Article
·
· Nucl. Saf.; (United States)
OSTI ID:5485697
The Water Reactor Analysis Package-Evaluation Model (WRAP-EM) is a modular system of computer codes designed to provide the safety analyst with the capability of performing complete loss-of-coolant calculations for both pressurized- and boiling-water reactor systems. The system provides a licensing-type calculation capability and thus contains most of the Nuclear Regulatory Commission-Approved EM options, as described in the Code of Federal Regulations, Title 10, Part 50, Appendix K. All phases of an accident (blowdown, refill, and reflood) are modeled. The WRAP consists of modified versions of five preexisting codes (RELAP4/MOD5, GAPCON, FRAP, MOXY, and NORCOOL), the necessary interfaces to permit automatic transition from one code to the next during the transient calculations, plus a host of user-convenience features to aid the analyst faced with a multitude of EM calculations. The WRAP has been verified against both calculated and experimental results.
- Research Organization:
- Savannah River Lab., Aiken, SC
- OSTI ID:
- 5485697
- Journal Information:
- Nucl. Saf.; (United States), Journal Name: Nucl. Saf.; (United States) Vol. 23:1; ISSN NUSAA
- Country of Publication:
- United States
- Language:
- English
Similar Records
WRAP-PWR-EM system development and applications
PWR loss-of-coolant accident analysis capability of the WRAP-EM system
The BWR Loss-of-Coolant Accident Analysis Capability of the Wrap-Em System
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5779331
PWR loss-of-coolant accident analysis capability of the WRAP-EM system
Technical Report
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:5320730
The BWR Loss-of-Coolant Accident Analysis Capability of the Wrap-Em System
Technical Report
·
Sat Mar 31 23:00:00 EST 1979
·
OSTI ID:6068988
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LICENSING
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
SAFEGUARD REGULATIONS
SAFETY
SIMULATION
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LICENSING
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
SAFEGUARD REGULATIONS
SAFETY
SIMULATION
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS