Systems aspects of reactor pressure vessel integrity: Executive report. Final report
Technical Report
·
OSTI ID:10115907
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
Reactor vessel integrity is affected by the following key issues: Operational heatup and cooldown pressure-temperature limit curves and the associated occurrence of low temperature over pressurization (LTOP); pressurized thermal shock (PTS) events that could lead to crack initiation in the vessel, and irradiation effects, including low upper shelf fracture toughness. Electric Power Research Institute`s Embrittlement Management Program is underway to develop methods in assessing reactor vessel integrity issues due to radiation embrittlement. Reactor vessel integrity may be impacted by different aspects including some degradation mechanisms. One of those aspects are the plant system changes associated with the reactor vessel. This report uses the results from various probabilistic analyses performed by Westinghouse and other organizations, to identify those plant systems which are most important to the reactor vessel embrittlement issues.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Westinghouse Electric Corp., Pittsburgh, PA (United States)
- Sponsoring Organization:
- Electric Power Research Inst., Palo Alto, CA (United States)
- OSTI ID:
- 10115907
- Report Number(s):
- EPRI-TR--103084-T1; ON: UN94005445
- Country of Publication:
- United States
- Language:
- English
Similar Records
Calculation of conditional reactor vessel fracture probabilities integrated over plant lifetime
Supplemental reactor vessel surveillance program guidelines: Joint EPRI-CRIEPI RPV embrittlement studies. Final report
Low-temperature overpressurization protection system setpoint analysis using RETRAN-02/MOD5 for Salem
Journal Article
·
· Nuclear Safety (Bimonthly Technical Progress Review); (United States)
·
OSTI ID:5078461
Supplemental reactor vessel surveillance program guidelines: Joint EPRI-CRIEPI RPV embrittlement studies. Final report
Technical Report
·
Mon Aug 01 00:00:00 EDT 1994
·
OSTI ID:10185842
Low-temperature overpressurization protection system setpoint analysis using RETRAN-02/MOD5 for Salem
Journal Article
·
Fri Dec 30 23:00:00 EST 1994
· Transactions of the American Nuclear Society
·
OSTI ID:89179
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
36 MATERIALS SCIENCE
360103
360106
CRACK PROPAGATION
CRACKS
EMBRITTLEMENT
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE DEPENDENCE
PRESSURE VESSELS
PRESSURIZATION
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR VESSELS
RELIABILITY
RISK ASSESSMENT
STEELS
TEMPERATURE DEPENDENCE
THERMAL SHOCK
TRANSIENTS
210200
36 MATERIALS SCIENCE
360103
360106
CRACK PROPAGATION
CRACKS
EMBRITTLEMENT
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE DEPENDENCE
PRESSURE VESSELS
PRESSURIZATION
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR VESSELS
RELIABILITY
RISK ASSESSMENT
STEELS
TEMPERATURE DEPENDENCE
THERMAL SHOCK
TRANSIENTS