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Some engineering aspects of the steam generator system for the United States LMFBR demonstration plant

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Abstract

This paper describes the main design features of the steam generator system for the Clinch River Breeder Reactor Plant and the engineering approach being employed for some of the critical elements of this system, including in particular the sodium-steam/water boundary, the efforts to have this boundary be of highest integrity, and the system features to safely accommodate any failure of the boundary. (author)
Authors:
Publication Date:
Jul 01, 1975
Product Type:
Conference
Report Number:
IWGFR-1
Reference Number:
EDB-00:099550
Resource Relation:
Conference: Study group meeting on steam generators for LMFBR's, Bensberg (Germany), 14-17 Oct 1974; Other Information: 5 refs, 4 figs; PBD: Jul 1975; Related Information: In: Study group meeting on steam generators for LMFBR's. Summary report, 334 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CLINCH RIVER BREEDER REACTOR; DESIGN; FAILURES; MOLTEN METAL-WATER REACTIONS; SODIUM; SPECIFICATIONS; STEAM GENERATORS
OSTI ID:
20107668
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0055688054505
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 49-53
Announcement Date:
Dec 01, 2000

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Citation Formats

Tippets, F E. Some engineering aspects of the steam generator system for the United States LMFBR demonstration plant. IAEA: N. p., 1975. Web.
Tippets, F E. Some engineering aspects of the steam generator system for the United States LMFBR demonstration plant. IAEA.
Tippets, F E. 1975. "Some engineering aspects of the steam generator system for the United States LMFBR demonstration plant." IAEA.
@misc{etde_20107668,
title = {Some engineering aspects of the steam generator system for the United States LMFBR demonstration plant}
 author = {Tippets, F E}
 abstractNote = {This paper describes the main design features of the steam generator system for the Clinch River Breeder Reactor Plant and the engineering approach being employed for some of the critical elements of this system, including in particular the sodium-steam/water boundary, the efforts to have this boundary be of highest integrity, and the system features to safely accommodate any failure of the boundary. (author)}
 place = {IAEA}
 year = {1975}
 month = {Jul}
 }