Survey of Primary Knock-on Atoms Characteristics and Radiation Damage in Stainless Steel Grade 316

Document Type : Research Paper

Authors

1 Ph.D. in Physics. Department of Physics, Arak University

2 Associate Professor, Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, AEOI

3 Associate Professor, Department of Physics, Arak University

4 Ph.D. in Nuclear Engineering. Institute of Reactor and Nuclear Safety, Arak University

Abstract

The displacement of the atoms from their lattice sites is one of the results of neutron irradiation on materials. The primary knocked-on atoms spectrum and their angular distribution should be calculated for consideration of neutron radiation damage calculation. The AMTRACK program has been developed to calculate this information. This program extracts and analyzes information about the primary knocked-on atoms by using Ptrac output of the MCNPX code. In this study, Stainless Steel 316, one of the most important alloys in the reactor pressure vessel, is investigated. The material is irradiated by single energy neutrons of 1keV to 10MeV, the fraction of produced PKAs, their average energy, their maximum energy, and radiation damage value are calculated. The calculations are performed by using the neutron spectrum of the Bushehr reactor. Using this method, the amount of damage in the Bushehr reactor pressure vessel (for Stainless Steel 316) is equal to 7.2×10-22 (dpa/ fluence).

Keywords


 
[1]    Was G.S., Fundamentals of radiation materials science, Metals and alloys., 1st ed. Springer, Berlin, 2007
[2]    Averback R.S., Atomic displacement processes in irradiated metals.,  Journal of nuclear materials, 216, 49-62, 1994
[3]    Vladimirov P., Bouffard S., Displacement damage and transmutations in metals under neutron and proton irradiation., Comptes Rendus Physique, 9, 303-322, 2008
[4]    Robinson M.T., Basic physics of radiation damage production., Journal of nuclear materials, 216, 1-28, 1994
[5]    Blue T., Lohan B., Khorsandi B. and Miller D., Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR., Journal of ASTM International, 3, 1-8, 2006
[6]    Herman M., Trkov A., Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII., Brookhaven National Laboratory, 1, 2010
[7]    Kapyrin P.G., Krylov S.Y., Album of neutronic characteristics of reactor core of the initial fuel inventory (for operation personnel of mcr)., Boston, 3, 2005
[8]    Jr. Karnoski Pj., Fretague Wj., Potapovs Uldis and Steele L.E., Stainless Steel Reactor Pressure Vessels., Nuclear Engineering and Design, 11, 347-367, 1970
[9]    Klueh R.L., Elevated-temperature ferritic and martensitic steels and their application to future nuclear reactors., Int. Mater. Rev., 50, 287-310, 2005
[10]IAEA-TECDOC-665, Materials for advanced water cooled reactors., Proceedings of a Technical Committee Meeting held in Plzeh, Czechoslovakia, 5, 14-17, 1991
[11]Gillemot F., Overview of reactor pressure vessel cladding., Int. J. Nuclear Knowledge Management4, 265-278, 2010
[12]Stegemann D., Reimche W., Feiste K.L., Reichert Ch., Bernard M., Weber W., characterization of reactor pressure vessel steels by magneto inductive harmonic analysis., NDT.net, 5No. 08, 2000
[13]Gilbert M.R., Marian J., Sublet j.Ch., Energy spectra of primary knock-on atoms under neutron irradiation, Journal of nuclear materials, 467, 121-134, 2015
[14]Luneville L., Simeone D., Gosset D., A new tool to compare neutron and ion irradiation in materials., Nuclear Instruments and methods in Physics B, 250, 71-75, 2006
[15]            Ghazi Ardakani S.F., Hadad K., Evaluation of radiation damage in belt-line region of VVER-1000 nuclear reactor pressure vessel., Progress in Nuclear Energy, 99, 96-102, 2017
[16]Ghazi Ardakani S.F., Hadad K., Monte Carlo evaluation of neutron irradiation damage to the VVER-1000 PRV., Nuclear Energy and Technology, 3, 73-80, 2017
[17]Amirkhani M.A., Asadi AsadAbad M., Hasanzadeh M., Mirvakili S.M., Mohamadi A., Calculation of dpa rate in graphite box of Tehran Research Reactor (TRR), Nuclear Science and Techniques, 30:92, 2019
[18]            Pelowitz D.B., MCNPX 2.7D Extensions., Los Alamos National Laboratory Report LA-UR-10-07031, 2010
[19]SAE International AMS 5524L, Steel Corrosion and Heat-Resistant Sheet Strip and Plate., SAE 30316 Solution Heat Treated, 2014
[20]Ziegler J.F., SRIM-2003., Nuclear Instrument and Methods in Physics Research Section B, 219, 1027-1036, 2004
[21]Ziegler J.F., Biersack J.P., Ziegler M.D. , SRIM The Stopping Range of Ions in matter, Ion Implantation Press, 15th ed, Boston, 4,  2008
[22]Ziegler J.F., Biersack J., Littmark U., The Stopping and Range of Ions in Matter., Treatise on Heavy-Ion Science, 99-129, 1985
[23]Ziegler J.F., Ziegler M.D., Biersak J.P., SRIM the Stopping Range of Ions in matter., Nuclear Instrument and Methods in Physics Research Section B, 268, 1818-1823,2010
[24]Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation, Annual Book of ASTM Standard, 17, E521-16