Methodology Used in the Integrated Assessment of PIUS-600 Safety
- Brookhaven National Lab. (BNL), Upton, NY (United States)
The revolutionary reactor design, PIUS-600 as described in the Preliminary Safety Analysis Report (PSID) was subject to analyses consisting of Failure Modes. Effects and Criticality Analysis (FMECA), Hazards and Operability (HAZOP) analysis, and conventional engineering review of the stress, neutronics, thermal hydraulics, and corrosion. These results were integrated in the PIUS Intermediate Table (PIT) from which accident initiators and mitigators were identified and categorized into seven estimated frequency intervals. Accident consequences were classified as: CC-1, minor radiological release, CC-2, clad release, CC-3, major release. The systems were analyzed using event sequence diagrams (ESDs) and event trees (ETs). The resulting accident sequences of the ET were categorized into event conditions (ECs) based on initiator frequency and combinations of failures. System interactions were considered in the FMECAs, ESDs, ETs and in an interaction table that also identified system safety classifications.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USNRC; USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10164430
- Report Number(s):
- BNL-NUREG-49052; CONF-930807-3; ON: DE93015791; TRN: 93:016430
- Resource Relation:
- Conference: 16. Biennial Conference on Reactor Operating Experience (OpE) , Upton, NY (United States), 16-18 Aug 1993; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PWR TYPE REACTORS
SAFETY ANALYSIS
REACTOR SAFETY
CRITICALITY
FAILURE MODE ANALYSIS
FAILURES
Nuclear Criticality Safety Program (NCSP)
Preliminary Safety Analysis Report (PSID)
Effects and Criticality Analysis (FMECA)
Hazards and Operability (HAZOP)
Pre-Stressed Concrete Vessel (PCRV)
PIUS Intermediate Table (PIT)
Event Sequence Diagrams (ESDs)
Event Trees (ETs)
Event Conditions (ECs)
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED