Email this article Long-term high-temperature exposure effects on mechanical properties and structure of the 42XNM alloy after neutron irradiation in the VVER-1000. Part 1. Mechanical tests
- Authors: Gurovich B.A.1, Frolov A.S.1, Kuleshova E.A.2, Fedotov I.V.1
-
Affiliations:
- National Research Center “Kurchatov Institute”
- National Research Nuclear University MEPhI
- Issue: No 1(113) (2023)
- Pages: 134-149
- Section: Radiation materials science
- URL: https://ogarev-online.ru/1994-6716/article/view/304962
- DOI: https://doi.org/10.22349/1994-6716-2023-113-1-134-149
- ID: 304962
Cite item
Open Access
Access granted
Subscription Access
Abstract
The paper presents the results of mechanical tests of ring specimens made of the 42XNM alloy after irradiation as part of the control and protection system of the VVER-1000 reactor to a damaging dose of ~12 dpa at a temperature of ~350°C and subsequent isothermal annealings in the temperature range of 400– 1150°C (heating and holding for ~2 h). A model was constructed and validated by the finite element method, it describes the mechanical characteristics of irradiated and non-irradiated samples from the 42XNM alloy during tests in the temperature range from 500 to 1000°C. The model was used to plot the temperature dependences of the maximum local plastic deformation and the yield strength of the material under study.
About the authors
B. A. Gurovich
National Research Center “Kurchatov Institute”
Author for correspondence.
Email: Frolov_AS@nrcki.ru
Dr Sc (Eng) 1 Akademika Kurchatova Square, 123182 Moscow, Russian Federation
A. S. Frolov
National Research Center “Kurchatov Institute”
Email: Frolov_AS@nrcki.ru
Cand Sc (Eng) 1 Akademika Kurchatova Square, 123182 Moscow, Russian Federation
E. A. Kuleshova
National Research Nuclear University MEPhI
Email: Frolov_AS@nrcki.ru
Dr Sc (Eng) 31 Kashirskoe shosse, 115409 Moscow, Russian Federation
I. V. Fedotov
National Research Center “Kurchatov Institute”
Email: Frolov_AS@nrcki.ru
1 Akademika Kurchatova Square, 123182 Moscow, Russian Federation
References
- Gurovich , B.A., Frolov, A.S., Kuleshova , E.A., Maltsev, D.A., Safonov, D.V., Microstructural evolution of the 42XNM alloy during a severe accident (LOCA), J. Nucl. Mater., 2022, V. 561, p. 153535.
- Ward , J.T., Witter, J.K., Angeliu , T.M., Assessing the effects of radiation damage on Ni-base alloys for the prometheus space reactor system, J. Nucl. Mater., 2007, V. 366, No 1-2, pp. 223-237.
- Solonin , M.I., Alekseev, A.B., Kazennov, Y.I., Khramtsov. V.F., Kondra t’ev, V.P., Krasina , T.A., Rechitsky, V.N., Stepankov, V.N., Votinov, S.N., XHM-1 alloy as a promising structural material for water-cooled fusion reactor components, J. Nucl. Mater., 1996, V. 233-237, Part 1, pp. 586- 591.
- Solonin , M.I., et al., Cr-Ni alloys for fusion reactors, J. Nucl. Mater., 1998, V. 258-263, Part 2, pp. 1762-1766.
- Gurovich , B.A., Frolov, A.S., Fedotov, I.V., Improved evaluation of ring tensile test ductility applied to neutron irradiated 42XNM tubes in the temperature range of 500-1100°C, Nucl. Eng. Technol., 2020, V. 52, No 6, pp. 1213-1221.
- Gurovich , B.A., Frolov, A.S., Kuleshova , E.A., Maltsev, D.A., Safonov, D.V., Fedotova , S.V., Kochkin , V.N., Panferov, P.P., Structural evolution features of the 42XNM alloy during neutron irradiation under VVER conditions, J. Nucl. Mater., 2021, V. 543, pp. 152557.
- Razumovskiy, V.I., Lozovoi, A.Y., Razumovskii, I.M., First-principles-aided design of a new Ni-base superalloy: Influence of transition metal alloying elements on grain boundary and bulk cohesion, Acta Mater., Acta Materialia Inc., 2015, V. 82, pp. 369-377.
- Frolov, A.S., Fedotov, I.V., Gurovich , B.A., Evaluation of the true-strength characteristics for isotropic materials using ring tensile test, Nucl. Eng. Technol. Elsevier, 2021, V. 53, No 7, pp. 2323-2333.
- Kleemola , H.J., Nieminen , M.A., On the strain-hardening parameters of metals, Metall. Trans., 1974, V. 5, pp. 1863-1866.
- Walley, S.M., The Effect of Temperature Gradients on Elastic Wave Propagation in Split Hopkinson Pressure Bars, J. of Dyn. Behav. of Mater., Springer International Publishing, 2020, V. 6, No 3, pp. 278-286.
- Barsoum I., Al Ali, K.F., Development of a method to determine the transverse stress-strain behaviour of pipes, Procedia Eng., 2015, V. 130, pp. 1319-1326.
- Nindiyasari, F., Pi erick , P., Boomstra , D., Pandit, A., Ring tensile test of reference zircaloy cladding tube as a proof of principle for hotcell setup, Proc.TopFuel-2018 Conf., Prague, Czech Repuublic, 2018.
- Campitelli, E., Assessment of mechanical properties in unirradiated and irradiated zircalloys and steels with non-standard tests and finite element calculations, Thesis No 3304, EPFL, Lausanne, 2005.
Supplementary files
