Helium and hydrogen generation in the structural materials (SM) of nuclear reactors is considered. The method to calculate the gases production is described. By applying the program code MMK, the neutron spectra in various positions including zones with different fuel enrichment and internals are calculated in BOR-60, MBIR, BN-800, BREST and WWER-SKD reactors and USDOE/JAERI experimental facility. Neutron fluxes in 299 energy groups are obtained. An analysis of experimental and evaluated (n,p) and (n,α) reaction excitation functions is performed for the main chemical elements of SM. The chemical elements with large incomes in helium and hydrogen generation are estimated. The main contributors in helium production are Ni and B and in hydrogen production is Ni.
Using FISPACT code, the helium and hydrogen generation rates are calculated in ChS139 ferritic-martensitic steel and in EK164 and 18Cr9Ni austenitic steels under neutron irradiation in different positions of these reactors. Differences in dose rates in some reactors or in helium and hydrogen generation rates can lead to significant differences in swelling of SM under irradiation in these reactors at the same temperatures and doses.
1. Grudzevich O.T., Pechenkin V.A., Kobetz U.A., Gurbich A.F., Bokhovko M.V., Shaginyan R.A., Margolin B.Z., Petrov S.N., Mikhailov M.S., Vasileva E.A. Issledovaniya radiatsionnoy stoykosti konstruktsionnykh materialov na uskoritelyakh ionov [Investigation of structural materials radiation resistance with ion accelerators]. Voprosy atomnoy nauki i tekhniki. Seriya: yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 3, pp. 127–145.
2. Tanaka T., Oka K., Ohnuki S. et al. Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe-Cr ferritic alloys. Journal of Nuclear Materials, 2004, vol. 329–333, pp. 294–297.
3. Wakai E., Sawai T., Furuya K. et al. Effect of triple ion beams in ferritic/martensitic steel on swelling behavior. Journal of Nuclear Materials, 2002, vol. 307–311, pp. 278–282.
4. Wakai E., Kikuchi K., Yamamoto S. et al. Swelling behavior of F82H steel irradiated by triple/dual ion beams. Journal of Nuclear Materials, 2003, vol. 318, pp. 267–273.
5. Sekimura N., Iwai T., Arai Y., Yonamine S., Naito A., Miwa Y., Hamada S. Synergistic effects of hydrogen and helium on microstructural evolution in vanadium alloys by triple ion beam irradiation. Journal of Nuclear Materials, 2000, vol. 283–287, pp. 224–228.
6. Forrest R., Sowerby M. and Endacott D. The Data Library UKACT1 and the Inventory Code FISPACT. Proc. of Int. Conf., Mito, Japan, 1988, p. 1061.
7. Grudzevich O.T., Zelenetskiy A.V., Ignatuyk A.V. Pashchenko A.B. Nuclear data library for activation and transmutation calculations. Atomic Energy, 1994, vol. 76, issue 2, pp. 119–122.
8. Grudzevich O.T., Zelenetskiy A.V., Ignatuyk A.V. Pashchenko A.B., Catalogue of ADL-3 library. Voprosy atomnoy nauki i tekhniki. Seriya: Yadernyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear Constants, 1993, issue 3–4, p. 3.
9. IkedaY., Kumar A., Konno C. Activation Cross Sections for the Generation of Long-Lived Radionuclides Importance in Fusion Reactor Technology. Proc. of an IAEA Consultants’ Meeting. Vienna, Austria, November, 1991.
10. Report INDC(NDS)-232/L. Activation Cross Sections for the Generation of Long-Lived Radionuclides Importance infusion Reactor Technology. Proc. of an IAEA Consultants’ Meeting held by Argonne National Laboratory, Argonne, USA, 11-12 September 1989.
11. Kumar A., Ikeda Y., Abdou A., et al. Induced Radioactivity Measurements in Fusion Neutron Environment – Joint Report of USDOE/JAERI Collaborative Program on Fusion Neutronics. JAERI-M-93-018, February, 1993.
12. Chadwick M.B., Gardner M.A., Gardner D.G., Grudzevich O.T. e. a. Intercomparison of Theoretical Calculations of Important Activation Cross Sections for Fusion Reactor Technology. Proc. IAEA Coordinated Meeting, Del Mar, USA, 1993, INDC(NDS)-286, p. 123.
13. Garner F.A. Chapter 6: “Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors”. Materials Science and Technology: A Comprehensive Treatment, VCH Publishers, 1994, vol. 10a, pp. 419–543.
14. Pechenkin V.A., Chernov K.G., Moiseev A.V., Eliseev V.A., Konobeev Yu.V. Kharakteristiki povrezhdayushchey dozy v metallakh i konstruktsionnykh materialakh pri obluchenii v aktivnoy zone reaktorov BN i VVER [Characteristics of Damage Dose in Metals and Structural Materials under Irradiation in the Core of BN and WWER Reactors]. Yadernaya fizika i inzhiniring – Nuclear Physics and Engineering, 2013, vol. 4, no. 3, pp. 262–272.
15. Garner F.A., Toloczko M.B., Sencer B.H. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure. Journal of Nuclear Materials, 2000, vol. 276, pp. 123–142.
16. Garner F.A., Gelles D.S., Greenwood L.R., Okita T., Sekimura N., Wolfer W.G. Synergistic influence of displacement rate and helium/dpa ratio on swelling of Fe–(9, 12)Cr binary alloys in FFTF at ≈ 400 °С. Journal of Nuclear Materials, 2004, vol. 329–333, pp. 1008–1012.
17. Budylkin N.I., Bulanova T.M., Mironova E.G. et al. The strong influence of displacement rate on void swelling in variants of Fe–16Cr–15Ni–3Mo austenitic stainless steel irradiated in BN-350 and BOR-60. Journal of Nuclear Materials, 2004, vol. 329–333, pp. 621–624.