Development of flaw evaluation and acceptance procedures for flaw indications in the cooling water system at the Savannah River Site K Reactor
- Westinghouse Electric Corp., Pittsburgh, PA (US)
- Westinghouse Savannah River Co., Aiken, SC (US)
This paper describes the methodology used in determining the criteria for acceptance of inspection indications in the K-Reactor Cooling Water System at the Savannah River Plant. These criteria have been developed in a manner consistent with the development of similar criteria in the ASME Code Section 11 for commercial light water reactors, but with a realistic treatment of the operating conditions in the cooling water system. The technical basis for the development of these criteria called {open_quotes}Acceptance Standards{close_quotes} is contained in this paper. A second portion of this paper contains the methodology used in the construction of flaw evaluation charts which have been developed for each specific line size in the cooling water system. The charts provide the results of detailed fracture mechanics calculations which have been completed to determine the largest flaw which can be accepted in the cooling water system without repair. These charts are designed for use in conjunction with inservice inspections of the cooling water system, and only require inspection results to determine acceptability.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10163288
- Report Number(s):
- WSRC-MS-93-262; CONF-930702-45; ON: DE93014731; TRN: 93:001633
- Resource Relation:
- Conference: 1993 American Society of Mechanical Engineers (ASME) pressure vessel and piping conference,Denver, CO (United States),25-29 Jul 1993; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
K REACTOR
REACTOR COOLING SYSTEMS
INSPECTION
STANDARDS
FRACTURE MECHANICS
WATER COOLED REACTORS
WELDED JOINTS
DEFECTS
PIPES
LEAKS
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
220600
210500
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
POWER REACTORS
BREEDING