Reactor analysis support package (RASP). Volume 1. Introduction and overview. Final report
Technical Report
·
OSTI ID:5859879
- ed.
The experience of recent years has demonstrated an ever-increasing need for utilities operating nuclear power plants to have the means to re-analyze those postulated events that form the bases for plant operation or safety design. The Reactor Analysis Support Package (RASP) provides an integrated, interlinked, and validated code package satisfying a wide range of nuclear utility applications. RASP consolidates existing core physics, thermal-hydraulics, and fuel performance computer codes into an integrated and self-consistent system. The RASP project also involves producing several guideline documents and conducting seminars/workshops to assist the utilities in applying the RASP code package. This report provides a RASP overview that is useful both as an introduction for the inexperienced nuclear power plant analyst and as a reference guide for analysis staff management and the experienced analyst. The discussions of potential RASP applications, analysis qualification, reload licensing evaluations, and quality assurance should also be useful to utility management who are planning their staffing requirements. An effort was made to keep this report as succinct as practicable while still providing the level of detail adequate to satisfy the report's objectives. 34 figs., 24 tabs.
- Research Organization:
- Levy (S.), Inc., Campbell, CA (USA)
- OSTI ID:
- 5859879
- Report Number(s):
- EPRI-NP-4498-Vol.1; ON: TI86920294
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor Analysis Support Package (RASP). Volume 2. BWR event analysis guidelines. Final report
EPRI reactor analysis support package
SIGTRAN: A kinetics linkage code for the Reactor Analysis Support Package (RASP): Final report
Technical Report
·
Thu May 01 00:00:00 EDT 1986
·
OSTI ID:5644866
EPRI reactor analysis support package
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6570097
SIGTRAN: A kinetics linkage code for the Reactor Analysis Support Package (RASP): Final report
Technical Report
·
Tue Feb 28 23:00:00 EST 1989
·
OSTI ID:6325617
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
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
DESIGN
ENERGY SOURCES
ENERGY TRANSFER
EVALUATION
FLUID MECHANICS
FUEL MANAGEMENT
FUELS
HEAT TRANSFER
HYDRAULICS
LICENSING
MATERIALS
MECHANICS
NUCLEAR FUELS
PERFORMANCE
PHYSICS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR FUELING
REACTOR LICENSING
REACTOR MATERIALS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
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
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
DESIGN
ENERGY SOURCES
ENERGY TRANSFER
EVALUATION
FLUID MECHANICS
FUEL MANAGEMENT
FUELS
HEAT TRANSFER
HYDRAULICS
LICENSING
MATERIALS
MECHANICS
NUCLEAR FUELS
PERFORMANCE
PHYSICS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR FUELING
REACTOR LICENSING
REACTOR MATERIALS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS