Reviewing the PIUS Reactor Design with Failure Modes Effects and Criticality Analysis. [Advanced Reactors]

Conference · Sun Jun 07 00:00:00 EDT 1992

OSTI ID:5759302

Fullwood, R. ^[1]; Shier, W. ^[1]; Van Tuyle, G. ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

Advanced reactors proposed for electric power generation in the next century are evolutionary,'' meaning that they are improvements on the present generation of light water reactors (LWRs) or "revolutionary'' indicating the use of principles for which there is little experience and regulatory precedence. Outstanding in the revolutionary category in the PIUS (Process Inherent Ultimate Safety) conceived by K. Hannerz. PIUS-600 is a 600 MWe pressurized water reactor with no control rods, no active ECCS, a prestressed concrete reactor vessel (PCRV) and designed to operate in a pressure suppression containment with the primary circulation by "wet'' variable-speed pumps. Brookhaven National Laboratory, assisting the USNRC in identifying safety-significant aspects of the design, has assembled a multi-discipline team consisting of experts in thermal-hydraulics, PRA, seismic, structural, material and ALARA for this examination. The systems analysis is being done two-fold: failure modes effects and criticality analyses (FMECA) and hazards and operability study (HAZOP). It is believed that the former bottom-up'' and the latter top-down'' methods complement each other to enhance completeness. This paper describes the FMECA methods that have been applied.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USNRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5759302
• Report Number(s): BNL-NUREG-45103; CONF-920606-13; ON: DE92010169
• Resource Relation: Conference: American Nuclear Society Annual Meeting , Boston, MA (United States), 7-12 Jun 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
DESIGN
CRITICALITY
FAILURE MODE ANALYSIS
FAILURES
REACTOR COMPONENTS
REACTOR OPERATION
REACTOR SAFETY
ENRICHED URANIUM REACTORS
OPERATION
POWER REACTORS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
Prestressed Concrete Reactor Vessel (PCRV)
PIUS (Process Inherent Ultimate Safety)
Failure Modes Effects and Criticality Analyses (FMECA)
Hazards and Operability Study (HAZOP)
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled