Reactor Vessel Materials

Code of Federal Regulations, Title 10, Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements."... 

EUR (1996a) A review of formulas for predicting irradiation embrittlement of reactor vessel materials , AMES Report N.6, EUR 16455 EN, European Commission DG XI/C/2. 

AR378 1.99 Radiation embrittlement of reactor vessel materials (Draft ME 305-4, Proposed revision 2,... 

The Code specifies that surveillance capsules shall be located within the reactor vessel so that the specimen history duplicates as closely as possible the neutron spectrum, the temperature history and the maximum neutron flux experienced by the reactor vessel. A sufficient number of surveillance capsules shall be provided to monitor the effect of neutron radiation on the reactor vessel materials, that is, the transition temperature shift, ARTndt and the decrease in USE throughout its operating period. A minimum number of capsules is specified depending on the predicted ARTndt value of each testing material at the inside surface of the beltUne of the reactor vessel. In this section, the Japanese surveillance tests program is reviewed. The details of the JEAC 4201 can be found elsewhere (Tomimatsu et al., 2006). Table 4.8 summarizes major revisions of the JEAC 4201. 

CFR (1973a), Title 10 Code of Federal Regulations, Part 50 (10 CFR 50), Appendix H, Reactor vessel material surveillance program requirements , US Nnclear Regulatory Commission, Washington, DC. 

ASTM E 900-02 (2002), Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF) , American Society for Testing and Materials. 

EPRI (2000), RPVDATA Reactor Vessel Materials Database, Version 2.0, SW-114785-CD, Electric Power Research Institute, Palo Alto, CA. 

NRC 19 ), Regulatory Guide 1.99 Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC. 

ASTM, ASTM-900-02, Standard Guide for predicting radiation-induced transition shifts for reactor vessel materials, E760(11F) , Annual Book of ASTM Standards, Vol.12.02, American Society for Testing and Materials, West Conshohocken, PA. 

NRC, Regulatory Guide 1.99, Revision 1, Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessels Materials , US Nuclear Regulatory Commission, Washington DC, April 1977. 

JJ. Koziol, Radiation surveillance program for Combustion Engineering, Inc. reactor vessel materials, In Steele, L.P. (Ed.), Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects, ASTM STP784, American Society for Testing and Materials, Philadelphia, PA, 1983, Chapter 3. 

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