Methodology Used in the Integrated Assessment of PIUS-600 Safety
Conference
·
OSTI ID:7368743
- 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 Laboratory (BNL), Upton, NY (United States)
- Sponsoring Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 7368743
- Report Number(s):
- BNL-NUREG-49052; CONF-930807--3; ON: DE93015791
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220900* -- Nuclear Reactor Technology-- Reactor Safety
CRITICALITY
ENRICHED URANIUM REACTORS
Effects and Criticality Analysis (FMECA)
Event Conditions (ECs)
Event Sequence Diagrams (ESDs)
Event Trees (ETs)
FAILURE MODE ANALYSIS
FAILURES
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Nuclear Criticality Safety Program (NCSP)
PIUS Intermediate Table (PIT)
POWER REACTORS
PWR TYPE REACTORS
Pre-Stressed Concrete Vessel (PCRV)
Preliminary Safety Analysis Report (PSID)
REACTOR SAFETY
REACTORS
SAFETY
SAFETY ANALYSIS
SYSTEM FAILURE ANALYSIS
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THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220900* -- Nuclear Reactor Technology-- Reactor Safety
CRITICALITY
ENRICHED URANIUM REACTORS
Effects and Criticality Analysis (FMECA)
Event Conditions (ECs)
Event Sequence Diagrams (ESDs)
Event Trees (ETs)
FAILURE MODE ANALYSIS
FAILURES
Hazards and Operability (HAZOP)
Nuclear Criticality Safety Program (NCSP)
PIUS Intermediate Table (PIT)
POWER REACTORS
PWR TYPE REACTORS
Pre-Stressed Concrete Vessel (PCRV)
Preliminary Safety Analysis Report (PSID)
REACTOR SAFETY
REACTORS
SAFETY
SAFETY ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS