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Title: Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I

Abstract

The Sodium Water Advanced Analysis Method computer code (SWAAM-I) is used to analyze the large-leak test data SWAT-3 Run-6. The SWAT-3 is the mockup of the secondary system of the Japanese breeder-reactor demonstration plant Monju. The steam-generator design for the Monju reactor was a helical-coil-tube type with a cover-gas space, and the SWAT-3 Run-6 Test vessel simulates this design of the steam generator. The objectives of this work are: (1) to examine the adequacy of the SWAAM-I code for the helical-coil-tube steam-generator system, (2) to understand and confirm the understanding of phenomena that have major design implications, and (3) to define needs for additional development of SWAAM-I code capabilities.

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
707238
Report Number(s):
ANL-CT-82-4
ON: TI82014779
DOE Contract Number:
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: DN: Portions of document are illegible; PBD: Feb 1982
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; MONJU REACTOR; STEAM GENERATORS; MOLTEN METAL-WATER REACTIONS; LEAKS; TUBES; TEST FACILITIES; MOCKUP; COMPUTER CALCULATIONS; REACTOR SAFETY; PRESSURE GRADIENTS; HYDRAULICS

Citation Formats

Shin, Y.W., and Lin, H.C. Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I. United States: N. p., 1982. Web. doi:10.2172/707238.
Shin, Y.W., & Lin, H.C. Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I. United States. doi:10.2172/707238.
Shin, Y.W., and Lin, H.C. Mon . "Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I". United States. doi:10.2172/707238. https://www.osti.gov/servlets/purl/707238.
@article{osti_707238,
title = {Analysis of large-leak test SWAT-3 Run-6 data by use of sodium-water-reaction analysis code SWAAM-I},
author = {Shin, Y.W. and Lin, H.C.},
abstractNote = {The Sodium Water Advanced Analysis Method computer code (SWAAM-I) is used to analyze the large-leak test data SWAT-3 Run-6. The SWAT-3 is the mockup of the secondary system of the Japanese breeder-reactor demonstration plant Monju. The steam-generator design for the Monju reactor was a helical-coil-tube type with a cover-gas space, and the SWAT-3 Run-6 Test vessel simulates this design of the steam generator. The objectives of this work are: (1) to examine the adequacy of the SWAAM-I code for the helical-coil-tube steam-generator system, (2) to understand and confirm the understanding of phenomena that have major design implications, and (3) to define needs for additional development of SWAAM-I code capabilities.},
doi = {10.2172/707238},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Feb 01 00:00:00 EST 1982},
month = {Mon Feb 01 00:00:00 EST 1982}
}

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