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Design basis for creep of zirconium alloy components in a fast neutron flux

Conference ·
OSTI ID:4011070
;
The Chalk River Nuclear Laboratory's experience with the creep of zirconium alloys in a neutron flux is described. Fast neutron flux changes the creep behavior of zirconium alloys and new design criteria for in-reactor applications are needed. From experimental results empirical relations describing the effects of neutron flux, stress, temperature, time, and anisotropy on creep rate were established. The relations are applied to the design of pressure tubes. (auth)
Research Organization:
Chalk River Nuclear Labs., Ont.
NSA Number:
NSA-33-026812
OSTI ID:
4011070
Country of Publication:
United States
Language:
English

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Related Subjects

*NIOBIUM ALLOYS-- PHYSICAL RADIATION EFFECTS
*ZIRCALOY 2-- PHYSICAL RADIATION EFFECTS
*ZIRCONIUM BASE ALLOYS-- PHYSICAL RADIATION EFFECTS
360106* --Materials--Metals & Alloys--Radiation Effects
ANISOTROPY
BINARY ALLOY SYSTEMS
CREEP
DESIGN
FAST NEUTRONS
N50240* --Metals
Ceramics
& Other Materials--Metals & Alloys--Radiation Effects
N77400 --Reactors--Power Reactors
Non-breeding
Otherwise Moderated or Unmoderated
NEUTRON FLUX
PRESSURE TUBES
STRESSES
TEMPERATURE DEPENDENCE
TIME DEPENDENCE