Author: J. C. TobinPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 62
Book Description
Progress on the Irradiation Damage to Reactor Metals Program
Author: J. C. TobinPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 62
Book Description
Radiation Damage Studies Program ETR Loop Materials Progress Report II
Author: M. S. RobinsonPublisher:
ISBN:
Category : Materials
Languages : en
Pages : 68
Book Description
Radiation Effects Program Semiannual Progress Report for Period Ending January 31, 1974
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Research on materials for liquid metal fast breeder reactors is reported along with similar research on thermonuclear reactor materials. Results of research on the radiation behavior of Al and Al alloys are also reported along with results of fundadamental studies of radiation damage in metals. (JRD).
Summaries of Fuels and Materials Development Programs
Author: William L. R. RicePublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 278
Book Description
Summaries of Fuels and Materials Development Program
Author: William L. R. RicePublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 286
Book Description
Irradiation Effects on Structural Alloys for Nuclear Reactor Applications
Author: A. L. BementPublisher: ASTM International
ISBN: 9780803100695
Category : Neutron flux
Languages : en
Pages : 571
Book Description
Reactor Materials
Author: Structural Materials for Generation IV Nuclear Reactors
Author: Pascal YvonPublisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686
Book Description
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area
The Effect of Nuclear Radiation on Structural Metals
Author: Frederic R. ShoberPublisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
Book Description
The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels
Author: Lendell E. SteelePublisher: ASTM International
ISBN: 9780803102637
Category : Technology & Engineering
Languages : en
Pages : 240
Book Description