Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel

Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel
Author: FA. Garner
Publisher:
Total Pages: 18
Release: 1994
Genre: Creep rupture
ISBN:

A titanium-modified austenitic type stainless steel was tested at three cold work levels to determine its creep and creep rupture properties under both thermal aging and neutron irradiation conditions. Both the thermal and irradiation creep behavior exhibit a complex non-monotonic relationship with cold work level that reflects the competition between a number of stress-sensitive and temperature dependent microstructural processes. Increasing the degree of cold work to 30% from the conventional 20% level was detrimental to its performance, especially for applications above 550°C. The 20% cold work level is preferable to the 10% level, in terms of both in-reactor creep rupture response and initial strength.

Influence of Cold Work Level on the Irradiation Creep and Creep Rupture of Titanium-modified Austenitic Stainless Steels

Influence of Cold Work Level on the Irradiation Creep and Creep Rupture of Titanium-modified Austenitic Stainless Steels
Author:
Publisher:
Total Pages: 20
Release: 1992
Genre:
ISBN:

A titanium-modified austenitic type stainless steel was tested at three cold work levels to determine its creep and creep rupture properties under both thermal aging and neutron irradiation conditions. Both the thermal and irradiation creep behavior exhibit a complex non-monotonic relationship with cold work level that reflects the competition between a number of stress-sensitive and temperature-dependent microstructural processes. Increasing the degree of cold work to 30% form the conventional 20% level was detrimental to its performance, especially for applications above 550°C. The 20% cold work level is preferable to the 10% level, in terms of both in- reactor creep rapture response and initial strength.

Irradiation Creep and Creep Rupture of Titanium-modified Austenitic Stainless Steels and Their Dependence on Cold Work Level

Irradiation Creep and Creep Rupture of Titanium-modified Austenitic Stainless Steels and Their Dependence on Cold Work Level
Author:
Publisher:
Total Pages: 29
Release: 1991
Genre:
ISBN:

A titanium-modified austenitic type stainless steel was tested at three cold work levels to determine its creep and creep rupture properties under both thermal aging and neutron irradiation conditions. Both the thermal and irradiation creep behavior exhibit a complex non-monotonic relationship with cold work level that reflects the competition between a number of stress-sensitive and temperature-dependent microstructural processes. Increasing the degree of cold work to 30% from the conventional 20% level was detrimental to its performance, especially for applications above 550°c. The 20% cold work level is preferable to the 10% level, in terms of both in-reactor creep rupture response and initial strength.

Materials for Nuclear Plants

Materials for Nuclear Plants
Author: Wolfgang Hoffelner
Publisher: Springer Science & Business Media
Total Pages: 502
Release: 2012-09-21
Genre: Technology & Engineering
ISBN: 1447129148

The clamor for non-carbon dioxide emitting energy production has directly impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, materials modeling and advanced materials testing will be described including design code considerations and non-destructive evaluation concepts. Including models for simple system dynamic problems and knowledge of current nuclear power plants in operation, Materials for Nuclear Plants: From Safe Design to Residual Life Assessments is ideal for students studying postgraduate courses in Nuclear Engineering. Designers on courses for code development, such as ASME or ISO and nuclear authorities will also find this a useful reference.