Reactor Analysis Support Package (RASP). Volume 2. BWR event analysis guidelines. Final report

Technical Report · Thu May 01 04:00:00 EDT 1986

OSTI ID:5644866

Engel, R E; Sorensen, J M; Fuller, E D; Ostenso, A L; Keller, L A

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 detailed guidelines for performing event analyses for BWR operating plants using the RASP codes. The primary intent of these guidelines is to provide guidance for performing safety analyses to meet the intent of the applicable regulations contained in Title 10 of the Code of Federal Regulations (10 CFR) for updating the reactor analysis portion of the safety analyses with specific emphasis on performing reactor core reload licensing analyses. Before using these guidelines and the RASP codes to analyze and predict the transient behavior of a BWR, the analyst must first understand the design and operation of the plant. Therefore, this report presents a general discussion of BWR design and operation with an emphasis on systems, components and structures that impact the behavior of events.

• Research Organization: Levy (S.), Inc., Campbell, CA (USA)
• OSTI ID: 5644866
• Report Number(s): EPRI-NP-4498-Vol.2; ON: TI86920345
• Country of Publication: United States
• Language: English

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BWR TYPE REACTORS
COMPUTER CODES
DESIGN
ENERGY SOURCES
FLUID MECHANICS
FUELS
HYDRAULICS
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NUCLEAR FUELS
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REACTORS
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THERMODYNAMICS
TRANSIENTS
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WATER MODERATED REACTORS