PWR full reactor coolant system decontamination qualification program: Decontamination and reirradation of PWR fuel assemblies. Final report
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
The objective of this study was to decontaminate fuel assemblies of a Westinghouse Pressurized Water Reactor (PWR) design employing two selected processes, LOMI and CAN-DEREM. A unique test loop and canister were designed and built to enable chemical decontamination of individual nuclear fuel assemblies at South Carolina Electric and Gas Company`s Virgil Summer site. The test loop was installed, tested, and used to apply the LOMI and CAN-DEREM processes to the individual new fuel assemblies and twice-burned fuel assemblies. Four fuel assemblies were treated with the chemical processes at the same conditions of flow, temperature, pressure and chemical environment as would exist on the fuel in the reactor vessel during a Full Reactor Coolant System Chemical Decontamination. All four assemblies plus four control assemblies underwent extensive visual and eddy current inspections before and after the chemical decontamination. The inspections were repeated when the fuel assemblies were removed after one full cycle of operation in the V. C. Summer Plant. In summary the fuel material post decontamination inspection results showed no deleterious effects and also showed that the fuel assemblies were acceptable for continued reactor service.
- 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:
- 10149332
- Report Number(s):
- EPRI-TR--103816; ON: UN94011386
- Country of Publication:
- United States
- Language:
- English
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