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Small water/steam leaks in sodium heated steam generators: Evaluation of the reaction zone - effects on 2 1/4 Cr 1 Mo structural material

Abstract

On the basis of experimental data the geometry of a small leak reaction zone can be predicted for given leak sizes and steam generator operation conditions. The effects of small leaks on 2 1/4 Cr 1 Mo material have been studied and completed with test results from foreign investigators. The results have to be considered as preliminary ones which have to be further qualified by additional information. (author)
Authors:
Publication Date:
Jul 01, 1975
Product Type:
Conference
Report Number:
IWGFR-1
Reference Number:
EDB-00:099561
Resource Relation:
Conference: Study group meeting on steam generators for LMFBR's, Bensberg (Germany), 14-17 Oct 1974; Other Information: 10 refs, 11 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; COMPARATIVE EVALUATIONS; EXPERIMENTAL DATA; LEAKS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEAM GENERATORS
OSTI ID:
20107679
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0055699054516
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 135-141
Announcement Date:
Dec 01, 2000

Citation Formats

Dumm, K. Small water/steam leaks in sodium heated steam generators: Evaluation of the reaction zone - effects on 2 1/4 Cr 1 Mo structural material. IAEA: N. p., 1975. Web.
Dumm, K. Small water/steam leaks in sodium heated steam generators: Evaluation of the reaction zone - effects on 2 1/4 Cr 1 Mo structural material. IAEA.
Dumm, K. 1975. "Small water/steam leaks in sodium heated steam generators: Evaluation of the reaction zone - effects on 2 1/4 Cr 1 Mo structural material." IAEA.
@misc{etde_20107679,
title = {Small water/steam leaks in sodium heated steam generators: Evaluation of the reaction zone - effects on 2 1/4 Cr 1 Mo structural material}
author = {Dumm, K}
abstractNote = {On the basis of experimental data the geometry of a small leak reaction zone can be predicted for given leak sizes and steam generator operation conditions. The effects of small leaks on 2 1/4 Cr 1 Mo material have been studied and completed with test results from foreign investigators. The results have to be considered as preliminary ones which have to be further qualified by additional information. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}