Fort St. Vrain proof test element number two design, fabrication, and assembly report
As part of the overall fuel ulement research and development program for the Public Service Company of Colorado Fort St. Vrain Nuclear Generatlng Station, Unit One Reactor, one or more prototype proof test fuel elements are to be irradiation tested in a high-temperature gas-cooled reactor (HTGR) environment. The design details, fuel characteristics, and assembly of the second proof test element (PTE-2) in a series of five prototype proof test elements built for the Fort St. Vrain Nuclear Generating Station are described. The purpose of the fue1 element irradiation program is to demonstrate that the Fort St. Vrain (FSV) fuel element will meet its design objectives. This will be demonstrated by irradiating a test element(s) in the Peach Bottom HTGR at temperature gradients typical of that expected in FSV to at least one-third of the design lifetime fuel burnup. PTE-2 will achieve the desired total burnup in approximately 300 full- power days of irradiation in Peach Bottom. It should be noted that PTE-2 was built in 1968, prior to the introduction of pitch-bonded, natural-flake graphite matrix which was eventually chosen for use in the FSV initial core. (25 references) (auth)
- Research Organization:
- Gulf General Atomic Co., San Diego, Calif. (USA)
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-29-020033
- OSTI ID:
- 4333759
- Report Number(s):
- GULF-GA-B--12340
- Country of Publication:
- United States
- Language:
- English
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