Published 1995
| Version v1
Book
A review of ventilated storage cask (VSC) system projects and experience
Description
First, the author discusses the ventilated storage cask (VSC) design and an operations summary is given. Next VSC project status at Palisades, Point Beach, Arkansas Nuclear One, Fast Flux Test Facility and Zaporozhye is discussed. Lastly, VSC operational experience and VSC transportation interfaces are reviewed
Additional details
Publishing Information
- Publisher
- Institute of Nuclear Materials Management.
- Imprint Place
- Northbrook, IL (United States)
- Imprint Title
- INMM spent fuel management seminar 12: Proceedings
- Imprint Pagination
- 277 p.
- Journal Page Range
- p. 17, Paper 6.
Conference
- Title
- 12. Institute of Nuclear Materials Management (INMM) spent fuel seminar.
- Dates
- 13-15 Jan 1995.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27047826
- Subject category
- S42: ENGINEERING; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ARKANSAS-1 REACTOR; DESIGN; DRY STORAGE; FFTF REACTOR; MATERIALS HANDLING EQUIPMENT; OCCUPATIONAL EXPOSURE; OPERATION; PALISADES-1 REACTOR; POINT BEACH-1 REACTOR; POINT BEACH-2 REACTOR; SPENT FUEL CASKS; SPENT FUEL STORAGE; ZAPOROZHE-1 REACTOR; ZAPOROZHE-2 REACTOR; ZAPOROZHE-3 REACTOR; ZAPOROZHE-4 REACTOR
- Descriptors DEC
- CASKS; CONTAINERS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STORAGE; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-950197--.