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Title: Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination

Abstract

The Steam Generator Few Tube Test (FTT) was part of an extensive testing program carried out in support of the Clinch River Breeder Reactor Plant (CRBRP) steam generator design. The testing of full-length seven-tube evaporator and three-tube superheater models of the CRBRP design was conducted to provide steady-state thermal/hydraulic performance data to full power per tube and to verify the absence of multi-year endurance problems. This paper describes the problems encountered with the mechanical features of the FTT model design which led to premature test termination, and the results of the post-test examination. Conditions of tube bowing and significant tube and tube support gouging was observed. An interpretation of the visual and metallurgical observations is also presented. The CRBRP steam generator has undergone design evaluations to resolve observed deficiences found in the FFTM.

Authors:
; ;
Publication Date:
Research Org.:
General Electric Co., Sunnyvale, CA (USA); Rockwell International Corp., Canoga Park, CA (USA)
OSTI Identifier:
6593402
Report Number(s):
CONF-810615-1
TRN: 81-009207
DOE Contract Number:  
AM03-76SF00893
Resource Type:
Conference
Resource Relation:
Conference: 2. joint US/Japan LMFBR steam generator seminar, Sunnyvale, CA, USA, 1 Jun 1981
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CLINCH RIVER BREEDER REACTOR; STEAM GENERATORS; HEAT TRANSFER; HYDRAULICS; PERFORMANCE TESTING; TEST FACILITIES; TUBES; BOILERS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; TESTING; VAPOR GENERATORS; 210500* - Power Reactors, Breeding

Citation Formats

Impellezzeri, J R, Camaret, T L, and Friske, W H. Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination. United States: N. p., 1981. Web.
Impellezzeri, J R, Camaret, T L, & Friske, W H. Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination. United States.
Impellezzeri, J R, Camaret, T L, and Friske, W H. 1981. "Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination". United States. https://www.osti.gov/servlets/purl/6593402.
@article{osti_6593402,
title = {Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination},
author = {Impellezzeri, J R and Camaret, T L and Friske, W H},
abstractNote = {The Steam Generator Few Tube Test (FTT) was part of an extensive testing program carried out in support of the Clinch River Breeder Reactor Plant (CRBRP) steam generator design. The testing of full-length seven-tube evaporator and three-tube superheater models of the CRBRP design was conducted to provide steady-state thermal/hydraulic performance data to full power per tube and to verify the absence of multi-year endurance problems. This paper describes the problems encountered with the mechanical features of the FTT model design which led to premature test termination, and the results of the post-test examination. Conditions of tube bowing and significant tube and tube support gouging was observed. An interpretation of the visual and metallurgical observations is also presented. The CRBRP steam generator has undergone design evaluations to resolve observed deficiences found in the FFTM.},
doi = {},
url = {https://www.osti.gov/biblio/6593402}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {3}
}

Conference:
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