Published June 10, 1975
| Version v1
Report
Restricted
Leaktightness in HTGRs: experience at Fort St. Vrain
Description
The Fort St. Vrain Prestressed Concrete Reactor Vessel is the first utilized to contain the helium coolant of a High Temperature Gas-Cooled Reactor. Because the helium coolant contains fission products, leakage from the vessel is limited to 15 percent of vessel inventory per year. The fabrication methods and development tests used to assure this leaktightness and the leakage test conducted to verify it are described. (U.S.)
Availability note (English)
MF available from INIS under the Report Number.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- GA-A--13383
Conference
- Title
- International conference on PCRVs.
- Dates
- 8 Sep 1975.
- Place
- York, UK.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7220594
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LEAK TESTING; LEAKS; PRESSURE VESSELS; VRAIN REACTOR
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTORS; TESTING
Optional Information
- Secondary number(s)
- CONF-750906--2.