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Assessment of materials for nuclear fuel immobilization containers

Abstract

A wide range of engineering metals and alloys has been assessed for their suitability as container materials for irradiated nuclear fuel intended for permanent disposal in a deep, underground hard-rock vault. The expected range of service conditions in the disposal vault are discussed, as well as the material properties required for this application. An important requirement is that the container last at least 500 years without being breached. The assessment is treated in two parts. Part I concentrates on the physical and mechanical metallurgy, with special reference to strength, weldability, potential embrittlement mechanisms and some economic aspects. Part II discusses possible mechanisms of metallic corrosion for the various engineering alloys and the expected range of environmental conditions in the vault. Localized corrosion and delayed fracture processes are identified as being most likely to limit container lifetime. Hence an essential requirement is that such processes either be absent or proceed at an insignificant rate. Three groups of alloys are recommended for further consideration as possible container materials: AISI 300 series austenitic stainless steels, high nickel-base alloys and very dilute titanium-base alloys. Specific alloys from each group are indicated as having the optimum combination of required properties, including cost. For container designs  More>>
Publication Date:
Sep 01, 1981
Product Type:
Technical Report
Report Number:
AECL-6440
Reference Number:
NTS-82-005793; ERA-07-035563; EDB-82-087990
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ALLOYS; COMPARATIVE EVALUATIONS; NICKEL BASE ALLOYS; RADIOACTIVE WASTE DISPOSAL; UNDERGROUND DISPOSAL; SPENT FUEL STORAGE; CONTAINERS; STAINLESS STEELS; TITANIUM BASE ALLOYS; BRINES; CORROSION; COST; FRACTURES; GROUND WATER; MATERIALS; MECHANICAL PROPERTIES; METALLURGY; PITTING CORROSION; SCREENING; SPENT FUELS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; ENERGY SOURCES; FAILURES; FUELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MANAGEMENT; NICKEL ALLOYS; NUCLEAR FUELS; OXYGEN COMPOUNDS; REACTOR MATERIALS; STEELS; STORAGE; TITANIUM ALLOYS; WASTE DISPOSAL; WASTE MANAGEMENT; WATER; 050900* - Nuclear Fuels- Transport, Handling, & Storage; 052002 - Nuclear Fuels- Waste Disposal & Storage
OSTI ID:
8142444
Research Organizations:
Atomic Energy of Canada Ltd., Pinawa, Manitoba. Whiteshell Nuclear Research Establishment
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE82902004
Availability:
NTIS (US Sales Only), PC A10/MF A01.
Submitting Site:
HEDB
Size:
Pages: 213
Announcement Date:
Feb 01, 1982

Citation Formats

Nuttall, K, and Urbanic, V F. Assessment of materials for nuclear fuel immobilization containers. Canada: N. p., 1981. Web.
Nuttall, K, & Urbanic, V F. Assessment of materials for nuclear fuel immobilization containers. Canada.
Nuttall, K, and Urbanic, V F. 1981. "Assessment of materials for nuclear fuel immobilization containers." Canada.
@misc{etde_8142444,
title = {Assessment of materials for nuclear fuel immobilization containers}
author = {Nuttall, K, and Urbanic, V F}
abstractNote = {A wide range of engineering metals and alloys has been assessed for their suitability as container materials for irradiated nuclear fuel intended for permanent disposal in a deep, underground hard-rock vault. The expected range of service conditions in the disposal vault are discussed, as well as the material properties required for this application. An important requirement is that the container last at least 500 years without being breached. The assessment is treated in two parts. Part I concentrates on the physical and mechanical metallurgy, with special reference to strength, weldability, potential embrittlement mechanisms and some economic aspects. Part II discusses possible mechanisms of metallic corrosion for the various engineering alloys and the expected range of environmental conditions in the vault. Localized corrosion and delayed fracture processes are identified as being most likely to limit container lifetime. Hence an essential requirement is that such processes either be absent or proceed at an insignificant rate. Three groups of alloys are recommended for further consideration as possible container materials: AISI 300 series austenitic stainless steels, high nickel-base alloys and very dilute titanium-base alloys. Specific alloys from each group are indicated as having the optimum combination of required properties, including cost. For container designs where the outer container shell does not independently support the service loads, copper should also be considered. The final material selection will depend primarily on the enviromental conditions in the vault. 42 figures, 31 tables.}
place = {Canada}
year = {1981}
month = {Sep}
}