Radiation damage concerns for extended light water reactor service

The objective of this paper is to examine the possible forms of irradiation damage that may impact materials performance over an extended service period in light water nuclear reactors. This paper will explore the different forms of irradiation damage that may be of concern under extended operation. Radiation-induced segregation, precipitation, hardening, embrittlement, and dimensional changes all will be discussed.

[1]  Stephen M. Bruemmer,et al.  Radiation-Induced Material Changes and Susceptibility to Intergranular Failure of Light-Water-Reactor Core Internals , 1999 .

[2]  P. J. Maziasz,et al.  Overview of microstructural evolution in neutron-irradiated austenitic stainless steels , 1993 .

[3]  E. Kenik,et al.  On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys , 1998 .

[4]  L. C. Walters,et al.  Status of LMR fuel development in the United States of America , 1993 .

[5]  Stephen M. Bruemmer,et al.  Emulation of neutron irradiation effects with protons: validation of principle , 2002 .

[6]  P. Maziasz,et al.  Microstructural evolution in annealed austenitic steels during neutron irradiation , 1987 .

[7]  P. J. Maziasz,et al.  Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels , 1989 .

[8]  E. Kenik Radiation-induced segregation in irradiated Type 304 stainless steels , 1992 .

[9]  Pj Maziasz Microstructural Stability and Control for Improved Irradiation Resistance and for High-Temperature Strength of Austenitic Stainless Steels , 1988 .

[10]  Gary S. Was,et al.  The relationship between hardness and yield stress in irradiated austenitic and ferritic steels , 2005 .

[11]  Steven J. Zinkle,et al.  Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel , 1993 .

[12]  A. Jenssen,et al.  Microchemical characterization of grain boundaries in irradiated steels , 1995 .

[13]  Stephen M. Bruemmer,et al.  Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS , 2003 .

[14]  B. L. Bramfitt,et al.  MiCon 86 : optimization of processing, properties, and service performance through microstructural control : a symposium , 1988 .