Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels ... Nureg/cr-6826 ... U.s. Nuclear Regulatory Commission
Author: Crack Growth Rates and Fracture Toughness of Irradiated Austenitic Stainless Steels in BWR Environments
Author: O. K. ChopraPublisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 0
Book Description
Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels
Author: O. K. ChopraPublisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 86
Book Description
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10{sup 21} n/cm{sup 2} (E> 1 MeV) ({approx}3.0 dpa) at {approx}288 C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288 C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of {approx}5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.
Fundamentals of Radiation Materials Science
Author: Gary S. WasPublisher: Springer Science & Business Media
ISBN: 3540494723
Category : Technology & Engineering
Languages : en
Pages : 827
Book Description
This book is an eye-opening treatise on the fundamentals of the effects of radiation on metals and alloys. When energetic particles strike a solid, numerous processes occur that can change the physical and mechanical properties of the material. Metals and alloys represent an important class of materials that are subject to intense radiation fields. Radiation causes metals and alloys to swell, distort, blister, harden, soften and deform. This textbook and reference covers the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys.
Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels
Author: Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels
Author: Y. ChenPublisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 0
Book Description
Structural Alloys for Nuclear Energy Applications
Author: Robert OdettePublisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 676
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Effects of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds
Author: Effect of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds
Author: O. K. ChopraPublisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 135
Book Description
Author: Omesh K. Chopra