Published 1974
| Version v1
Report
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Trip report: United States LMFBR Steam Generator Team. IAEA symposium, Bensberg, Germany, October 14--17, 1974
Description
Information is presented concerning steam generator design characteristics for the AFR reactor, SNR reactor, PHENIX reactor, SUPER PHENIX reactor, MONJU reactor, and BN-350 reactor; steam generator development programs for West Germany, France, Japan, U. K., and the U. S. S. R.; and the fabrication and inspection of steam generator components. Steam generator performance and maintenance requirements for operating LMFBR reactors are reviewed. (U.S.)
Availability note (English)
MF available from INIS under the Report Number.Files
7225562.pdf
Files
(2.9 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 74 p.
- Report number
- ERDA--36
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7225562
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BN-350 REACTOR; FABRICATION; FRANCE; GERMAN FEDERAL REPUBLIC; JAPAN; LMFBR TYPE REACTORS; MONJU REACTOR; PERFORMANCE; PFR REACTOR; PHENIX REACTOR; SNR REACTOR; SPECIFICATIONS; STEAM GENERATORS; SUPER PHENIX REACTOR; TESTING; UNITED KINGDOM; USSR
- Descriptors DEC
- ASIA; BOILERS; BREEDER REACTORS; DESALINATION REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; VAPOR GENERATORS