Fort St. Vrain nuclear generating station construction and testing experience
Journal Article
·
· Nuclear Engineering and Design
The 330 MW(e) Fort St. Vrain Nuclear Generating Station uses a uranium -- thorium fuel cycle; graphite for the moderator, fuel cladding, core structure, and reflector; and helium for the primary coolant. Significant design features are the prestressed concrete reactor pressure vessel, once-through modular steam generators with integral superheaters and reheaters, steam-driven axial flow helium circulators, and hexagonal graphite fuel elements incorporating improved carbon-coated fuel particles. Plant features, construction procedures, preliminary operating tests, fuel loading and startup procedures, and operator training programs are described.
- Research Organization:
- General Atomic Co., San Diego, CA
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-29-026066
- OSTI ID:
- 4324774
- Journal Information:
- Nuclear Engineering and Design, Vol. 26, Issue 1; Other Information: Orig. Receipt Date: 30-JUN-74; ISSN 0029-5493
- Publisher:
- Elsevier
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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