SCDAP/RELAP5 Evaluation of the Potential for Steam Generator Tube Ruptures as a Result of Severe Accidents in Operating PWRs
Description
Natural circulation flows can develop within a reactor coolant system (RCS) during certain severe reactor accidents, transferring decay energy from the core to other parts of the RCS. The associated heatup of RCS structures can lead to pressure boundary failures; with notable vulnerabilities in the pressurizer surge line, the hot leg nozzles, and the steam generator (SG) tubes. The potential for a steam generator tube rupture (SGTR) is of particular concern because fission products could be released to the environment through such a failure. The Nuclear Regulatory Commission (NRC) developed a program to address SG tube integrity issues in operating pressurized water reactors (PWRs) based on the possibility for environmental release. An extensive effort to evaluate the potential for accident-induced SGTRs using SCDAP/RELAP5 at the Idaho National Engineering and Environmental Laboratory (INEEL) was directed as one part of the NRC program. All SCDAP/RELAP5 calculations performed during the INEEL evaluation were based on station blackout accidents (and variations thereof) because those accidents are considered to be one of the more likely scenarios leading to natural circulation flows at temperatures and pressures that could threaten SG tube integrity (as well as the integrity of other vulnerable RCS pressure boundaries). Variations that were addressed included consideration of the effects of RCP seal leaks, intentional RCS depressurization through pressurizer PORVs, SG secondary depressurization, DC-HL bypass flows, U-tube SG sludge accumulation, and quenching of upper plenum stainless steel upon relocation to the lower head. Where available, experimental data was used to guide simulation of natural circulation flows. Independent reviews of the applicability of the natural circulation experimental data, the suitability of the code, and the adequacy of the modeling were completed and review recommendations were incorporated into the evaluation within budget and schedule limitations.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- INEEL/EXT--98-00286
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 39005115
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; COOLANTS; DECAY; DEPRESSURIZATION; FISSION PRODUCTS; NATURAL CONVECTION; NOZZLES; OUTAGES; PRESSURIZERS; PWR TYPE REACTORS; QUENCHING; REACTOR ACCIDENTS; RUPTURES; SCHEDULES; SLUDGES; STAINLESS STEELS; STEAM GENERATORS; SURGES
- Descriptors DEC
- ACCIDENTS; ALLOYS; BOILERS; CARBON ADDITIONS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; HEAT TRANSFER; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MASS TRANSFER; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- AC07-99ID-13727
- Notes
- doi 10.2172/911021
- Funding organization
- US Department of Energy (United States)