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Title: The Behaviour Of Zirconium Alloys In Santowax OM Organic Coolant At High Temperature

Abstract

Zirconium alloys have been exposed to Santowax OM at temperatures of 320 to 400 deg C for times as long as 5000 hours. Short-term experiments (less than 2 weeks) were done in stainless-steel bombs and small out-of-pile loops. The X-7 organic loop in the NRX reactor was used to study long-term oxidation and hydriding both in-flux and out-of-flux. The results obtained lead to several tentative conclusions. 1. Aluminum cladding serves as an effective hydrogen barrier. 2. Considerable protection against hydriding is given by zirconium oxide, provided impurities in the organic are carefully controlled. Hydriding is greatly enhanced by the presence of chlorine in the coolant. 4. Hydriding is somewhat enhanced by neutron irradiation. Of considerable significance is the fact that a Zircaloy-4 in-reactor test section of the X-7 loop was exposed to Santowax OM at 320 to 400 deg C for more than 5000 hours without excessive hydriding. (auth)

Authors:
Publication Date:
Research Org.:
Atomic Energy of Canada Ltd. Whiteshell Nuclear Research Establishment, Pinawa, Manitoba (Canada)
OSTI Identifier:
4657810
Report Number(s):
AECL-2118
NSA Number:
NSA-19-013911
Resource Type:
Technical Report
Country of Publication:
Canada
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; Corrosion; ALUMINUM; BARRIERS; CHLORINE; CORROSION; CORROSION PROTECTION; FUEL CANS; HYDRIDES; HYDROGEN; IMPURITIES; IN PILE LOOPS; NEUTRON BEAMS; NIOBIUM ALLOYS; NRX; ORGANIC COOLANT; OXIDATION; POLYPHENYLS; RADIATION EFFECTS; REACTORS; SANTOWAX; STAINLESS STEELS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM OXIDES; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

Sawatzky, A. The Behaviour Of Zirconium Alloys In Santowax OM Organic Coolant At High Temperature. Canada: N. p., 1964. Web.
Sawatzky, A. The Behaviour Of Zirconium Alloys In Santowax OM Organic Coolant At High Temperature. Canada.
Sawatzky, A. Thu . "The Behaviour Of Zirconium Alloys In Santowax OM Organic Coolant At High Temperature". Canada. https://www.osti.gov/servlets/purl/4657810.
@article{osti_4657810,
title = {The Behaviour Of Zirconium Alloys In Santowax OM Organic Coolant At High Temperature},
author = {Sawatzky, A.},
abstractNote = {Zirconium alloys have been exposed to Santowax OM at temperatures of 320 to 400 deg C for times as long as 5000 hours. Short-term experiments (less than 2 weeks) were done in stainless-steel bombs and small out-of-pile loops. The X-7 organic loop in the NRX reactor was used to study long-term oxidation and hydriding both in-flux and out-of-flux. The results obtained lead to several tentative conclusions. 1. Aluminum cladding serves as an effective hydrogen barrier. 2. Considerable protection against hydriding is given by zirconium oxide, provided impurities in the organic are carefully controlled. Hydriding is greatly enhanced by the presence of chlorine in the coolant. 4. Hydriding is somewhat enhanced by neutron irradiation. Of considerable significance is the fact that a Zircaloy-4 in-reactor test section of the X-7 loop was exposed to Santowax OM at 320 to 400 deg C for more than 5000 hours without excessive hydriding. (auth)},
doi = {},
journal = {},
number = ,
volume = ,
place = {Canada},
year = {1964},
month = {10}
}

Technical Report:

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