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Sodium-water reaction studies for MONJU steam generators

Abstract

The R and D results of the PNC's sodium-water reaction project are reviewed. The purposes of the project with the specific object for each test rig and computer code are given. The test items which should be investigated for the safety evaluation of the MONJU steam generators are discussed, and the status of the PNC's work on each item is described. The results on the small-leak wastage measurement are shown and the improved experimental equations to predict the wastage rate from the leak rate and the sodium temperature are given. The preliminary results on the wastage of tube bundle in the intermediate leak range are shown. The depth and the area of the wastage and also the wastage rate for each tube are shown graphically. The measured peak value of the initial pressure spike for the large leak is shown. The scatter of the data and its causes are discussed. The bubble growth rate estimated from the void probe measurement is presented. The results of the simulation experiment on the pressure wave propagation to the secondary circuit are given, comparing them with the prediction by the one-dimensional computer codes SWAC-5K and SWAC-5H. (author)
Publication Date:
Jul 01, 1975
Product Type:
Conference
Report Number:
IWGFR-1
Reference Number:
EDB-00:099555
Resource Relation:
Conference: Study group meeting on steam generators for LMFBR's, Bensberg (Germany), 14-17 Oct 1974; Other Information: 9 refs, 16 figs, 1 tab; 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; JAPANESE ORGANIZATIONS; LEAK TESTING; LEAKS; MOLTEN METAL-WATER REACTIONS; MONJU REACTOR; S CODES; SIMULATION; SODIUM; STEAM GENERATORS
OSTI ID:
20107673
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0055693054510
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 81-91
Announcement Date:

Citation Formats

Hori, M, Sato, M, Nei, H, Harasaki, T, Hishida, M, and Saito, T. Sodium-water reaction studies for MONJU steam generators. IAEA: N. p., 1975. Web.
Hori, M, Sato, M, Nei, H, Harasaki, T, Hishida, M, & Saito, T. Sodium-water reaction studies for MONJU steam generators. IAEA.
Hori, M, Sato, M, Nei, H, Harasaki, T, Hishida, M, and Saito, T. 1975. "Sodium-water reaction studies for MONJU steam generators." IAEA.
@misc{etde_20107673,
title = {Sodium-water reaction studies for MONJU steam generators}
author = {Hori, M, Sato, M, Nei, H, Harasaki, T, Hishida, M, and Saito, T}
abstractNote = {The R and D results of the PNC's sodium-water reaction project are reviewed. The purposes of the project with the specific object for each test rig and computer code are given. The test items which should be investigated for the safety evaluation of the MONJU steam generators are discussed, and the status of the PNC's work on each item is described. The results on the small-leak wastage measurement are shown and the improved experimental equations to predict the wastage rate from the leak rate and the sodium temperature are given. The preliminary results on the wastage of tube bundle in the intermediate leak range are shown. The depth and the area of the wastage and also the wastage rate for each tube are shown graphically. The measured peak value of the initial pressure spike for the large leak is shown. The scatter of the data and its causes are discussed. The bubble growth rate estimated from the void probe measurement is presented. The results of the simulation experiment on the pressure wave propagation to the secondary circuit are given, comparing them with the prediction by the one-dimensional computer codes SWAC-5K and SWAC-5H. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}