Author: W. R. CorwinPublisher:
ISBN:
Category : Government publications
Languages : en
Pages : 76
Book Description
Assessment of Radiation Effects Relating to Reactor Pressure Vessel Cladding
Author: W. R. CorwinPublisher:
ISBN:
Category : Government publications
Languages : en
Pages : 76
Book Description
Analysis of Reactor Vessel Radiation Effects Surveillance Programs
Author: Lendell E. SteelePublisher: ASTM International
ISBN: 9780803100664
Category : Freshwater microbiology
Languages : en
Pages : 269
Book Description
Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects
Author: Lendell E. SteelePublisher: ASTM International
ISBN: 9780803102293
Category : Technology & Engineering
Languages : en
Pages : 290
Book Description
Radiation Damage Surveillance of Power Reactor Pressure Vessels
Author: C. Z Serpan (Jr)Publisher:
ISBN:
Category :
Languages : en
Pages : 23
Book Description
The deleterious effect of high energy neutrons upon the mechanical properties of reactor pressure vessel steels has prompted the employment of material surveillance programs in many nuclear power plants. These programs provide for the exposure of test specimens representative of the reactor pressure vessel at in-reactor locations, wherein they will experience the same thermal and radiation damage history as the vessel itself. Evaluation of these specimens, which reveals the progressive changes in the mechanical properties of the vessel, provides a basis upon which operational procedures and maximum lifetime exposure may be formulated for the plant. A review and an analysis of several instances of shortcomings in surveillance programs are presented along with a set of recommendations for consideration in planning new surveillance programs. In utilizing these recommendations, pressure vessel surveillance programs can be made to provide valuable information for use in determining plant operations; at the same time results from these programs may add to the general knowledge of radiation effects in pressure vessel steels or other materials subject to radiation. Recognition of the value of surveillance programs and their conscientious application should further the public acceptance of nuclear reactors as safe alternative power systems.
Reactor Safety Study
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 660
Book Description
Status of Usa Neuclear Reactor Pressure Vessel Surveillance for Radiation Effects
Author: Procedures for Interpreting the Structural Implications of Radiation-Damage Surveillance Results on Nuclear Pressure Vessels
Author: L. E. SteelePublisher:
ISBN:
Category :
Languages : en
Pages : 21
Book Description
The structural implications of radiation effects to nuclear reactor pressure vessels are assessed primarily through surveillance programs in which the properties of the vessel are projected from an evaluation of small specimens of the vessel steel. In the USA, the current fracture-safe criterion requires that the vessel operating temperature, at certain stress levels, be at the FTE (Fracture Transition Elastic) temperature, defined as NDT+60F(33C), derived from surveillance measurements. Review of available data from five reactor surveillance programs indicates that this criterion is adequate for the vessels concerned. Complete assurance of fracture-safe operating conditions can be attained through a limit-analysis procedure that considers and integrates the effects of five factors: (a) the radiation-induced shift in transition temperature, (b) the initial shelf energy, (c) the radiation-reduced ductile shelf energy, (d) the effects of the fluence (and toughness) gradient through a thick vessel wall, and (3) the effects of thickness-induced mechanical constraint. (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
Proceedings of the U.S. Nuclear Regulatory Commission Thirteenth Water Reactor Safety Research Information Meeting, Held at National Bureau of Standards, Gaithersburg, Maryland, October 22-25, 1985: Materials engineering research, Environmental effects in piping, Surry steam generator
Author: Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
Author: Lendell E. SteelePublisher: ASTM International
ISBN: 0803104731
Category : Boiling water reactors
Languages : en
Pages : 303
Book Description