[1] Wikipedia, online encyclopedia, https://www.wikipedia.org (accessed November 20, 2014)
[2] Tribble, A.C., the Space Environment: Implications for Spacecraft Design, Princeton University Press, 2003.
[3] Kleiman, J.I., Z. Iskanderova, “Protection of Materials and Structures from Space Environment.” Proceedings of ICPMSE-6, Kluwer Academic Publishers, 2004.
[4] James, K.F., R.W. Norton, M.B. Alexander. The Natural Space Environment: Effects on Spacecraft, NASA Reference Publication 1350, 1994.
[5] Reimers, W., A.R. Pyzalla, A.K. Schreyer, H. Clemens. Neutrons and Synchrotron Radiation in Engineering Materials Science, Wiley-VCH, Germany, 2008.
[6] Margolin, B., A. Sorokin, V. Smirnov, V. Potapova. “Physical and Mechanical Modelling of Neutron Irradiation Effect on Ductile Fracture. Part 1.Prediction of Fracture Strain and Fracture Toughness of Austenitic Steels.” Journal of Nuclear Materials, xxx, xxx-xxx, 2014.
[7] Chen, Y. Irradiation Effects of HT-9 Martensitic Steel, Nuclear Engineering Division, Argonne National Laboratory, Argonne, IL 60439, USA, 2013.
[8] Norgett, M.J., M.T. Robinson, I.M. Torrens. “A Proposed Method of Calculating Displacement Dose Rates.” Nuclear Engineering and Design, 33, pp. 50-54, 1975.
[9] Byun, T.S., M.B. Toloczko, T.A. Saleh, S.A. Maloy. “Irradiation Dose and Temperature Dependence of Fracture Toughness in High Dose HT9 Steel from the Fuel Duct of FFTF.” Journal of Nuclear Materials, 432, pp. 1-8, 2013.
[10] Cockeram, B.V., T.S. Byun, K.J. Leonard, J.L. Hollenbeck, L.L. Snead. “Post-irradiation fracture toughness of Unalloyed Molybdenum, ODS Molybdenum, and TZM Molybdenum Following Irradiation at 244 to 507.” Journal of Nuclear Materials, 440, pp. 382-413, 2013.
[11] Xu, W., Y. Zhang, G. Cheng, W. Jian, P.C. Millett, C.C. Koch, S.N. Mathaudhu, Y. Zhu. “In-situ Atomic-scale Observation of Irradiation-induced Void Formation.” Nature Communications, DOI: 10.1038/ncomms3288, 2013.
[12] Krishna, S., S. De. “A temperature and Rate-dependent Micromechanical Model of molybdenum under Neutron irradiation.” Journal of Mechanics of Materials 43, pp. 99–110, 2011.
[13] Kalinin, G.M., A.S. Artyugin, M.V. Yvseev, V.V. Shushlebin, L.P. Sinelnikov, Y.S. Strebkov. “The Effect of Irradiation on Tensile Properties and Fracture Toughness of CuCrZr and CuCrNiSi alloys.” Journal of Nuclear Materials 417, pp. 908-911, 2011.
[14] Chopra, O.K., A. S. Rao. “A Review of Irradiation Effects on LWR Core Internal Materials-IASCC Susceptibility and Crack Growth rates of Austenitic Stainless Steels.” Journal of Nuclear Materials 409, pp. 235–256, 2011.
[15] Chen, Y., O.K. Chopra, W.K. Soppet, W.J. Shack, Y. Yang, T. Allen, A.S. Rao. “Cracking Behavior and Microstructure of Austenitic Stainless Steels and Alloys 690 Irradiated in BOR-60 Reactor, Phase I.” The Report of Argonne National Laboratory, Nuclear Engineering division, U. S. Department of Energy, 2007.
[16] Allen, T.R., J.I. Cole, C.L. Trybus, D.L. Porter, H. Tsai, F. Garner, E.A. Kenik, T. Yoshitake, J. Ohta. “The Effect of Dose Rate on the Response of Austenitic Stainless Steels to Neutron Radiation.” Journal of Nuclear Materials 348, pp. 148–164, 2006.
[17] Maloy, S.A., M.B. Toloczko, K. J. McClellan, T. Romero, Y. Kohno, F. A. Garner, R. J. Kurtz and A. Kimura, “The Effects of Fast Reactor Irradiation Conditions on the Tensile Properties of two Ferritic/Martensitic Steels.” Journal of Nuclear Materials 356, pp. 62–69, 2006.
[18] Klueh, R.L., N. Hashimoto, M.A. Sokolov, K. Shiba, S. Jitsukawa. “Mechanical properties of Neutron-irradiated Nickel-containing Martensitic Steels: I. Experimental Study.” Journal of Nuclear Materials 357, pp. 156–168, 2006.
[19] Klueh, R.L., N. Hashimoto, M.A. Sokolov, K. Shiba, P.J. Maziasz, S. Jitsukawa. “Mechanical Properties of Neutron-irradiated Nickel-containing Martensitic Steels: II. Review and Analysis of Helium-effects Studies.” Journal of Nuclear Materials 357, pp. 169–182, 2006.
[20] X. Jia, Y. Dai. “The Change of Fracture Toughness of Martensitic Steels after Irradiation in SINQ Target-3.” Journal of Nuclear Materials 356, pp. 50–55, 2006.
[21] Yamamoto, T., G.R. Odette, H. Kishimoto, J.W. Rensman, P. Miao “On the Effects of Irradiation and Helium on the Yield Stress Changes and Hardening and Non-hardening Embrittlement of 8Cr Tempered Martensitic Steels: Compilation and Analysis of Existing Data.” Journal of Nuclear Materials 356, pp. 27-49, 2006.
[22] Allen, T.R., H. Tsai, J.I. Cole, J. Ohta, K. Dohi, Hideo Kusanagi. Proceedings of ICONE10 10TH International Conference on Nuclear Engineering, ICONE-10. ASME, Arlington, VA, USA, 2002.
[23] Hirose, T., H. Tanigawa, M. Ando, A. Kohyama, Y. Katoh, M. Narui. “Radiation Effects on Low Cycle Fatigue Properties of Reduced Activation Ferritic/Martensitic Steels.” Journal of Nuclear Materials 307–311, pp. 304–307, 2002.
[24] Stoller, R.E., S.J. Zinkle. “On the Relationship between Uniaxial Yield Strength and Resolved Shear Stress in Polycrystalline Materials.” Journal of Nuclear Materials 283-287, pp. 349-352, 2000.
[25] Was, G.S. Fundamentals of Radiation Materials Science, Metals and Alloys, Springer, Materials Science and Engineering, University of Michigan, USA, 2007.
[26] Dissemination of IT for the Promotion of Materials Science, http://www.doitpoms.ac.uk. (accessed November 14, 2014)