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Questions raised in developing fast reactor steam generator designs

Abstract

The most important component in the achievement of satisfactory LMFBR reliability is the steam generator. When the failure statistics of other nuclear steam generators and the implications of a sodium water reaction are considered, there is some cause for concern. It is apparent that considerable improvement in technology is necessary and until more experience on operating plant is available a conservative design approach must be taken. Many solutions have been proposed, varying from forced circulation straight tube modular to large single vessel once through helical designs. The paper poses what are considered to be the main questions which arise when making a choice of fast reactor steam generator type and tube configuration. The aim is to promote discussion amongst the assembled experts on their relative design approaches and the importance placed upon the various factors in reaching our common goal of ensuring the success of the LMFBR in its essential role of conserving world energy resources. (author)
Publication Date:
Jul 01, 1975
Product Type:
Conference
Report Number:
IWGFR-1
Reference Number:
EDB-00:099592
Resource Relation:
Conference: Study group meeting on steam generators for LMFBR's, Bensberg (Germany), 14-17 Oct 1974; Other Information: 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; FORCED CONVECTION; LMFBR TYPE REACTORS; MOLTEN METAL-WATER REACTIONS; RELIABILITY; SAFETY ANALYSIS; SODIUM; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS; TUBES
OSTI ID:
20107710
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0055730054547
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 313-316
Announcement Date:

Citation Formats

Taylor, P A, and Hayden, O. Questions raised in developing fast reactor steam generator designs. IAEA: N. p., 1975. Web.
Taylor, P A, & Hayden, O. Questions raised in developing fast reactor steam generator designs. IAEA.
Taylor, P A, and Hayden, O. 1975. "Questions raised in developing fast reactor steam generator designs." IAEA.
@misc{etde_20107710,
title = {Questions raised in developing fast reactor steam generator designs}
author = {Taylor, P A, and Hayden, O}
abstractNote = {The most important component in the achievement of satisfactory LMFBR reliability is the steam generator. When the failure statistics of other nuclear steam generators and the implications of a sodium water reaction are considered, there is some cause for concern. It is apparent that considerable improvement in technology is necessary and until more experience on operating plant is available a conservative design approach must be taken. Many solutions have been proposed, varying from forced circulation straight tube modular to large single vessel once through helical designs. The paper poses what are considered to be the main questions which arise when making a choice of fast reactor steam generator type and tube configuration. The aim is to promote discussion amongst the assembled experts on their relative design approaches and the importance placed upon the various factors in reaching our common goal of ensuring the success of the LMFBR in its essential role of conserving world energy resources. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}