A Study of Irradiation-Induced Growth of Modified and Advanced Zr-Nb System Alloys after Irradiation in the VVER-1000 Reactor Core at Temelin NPP-Reference-Cited by-同舟云学术

A Study of Irradiation-Induced Growth of Modified and Advanced Zr-Nb System Alloys after Irradiation in the VVER-1000 Reactor Core at Temelin NPP

Published:2023-11-01 Issue: Volume: Page:520-539
ISSN:
Container-title:Zirconium in the Nuclear Industry: 20th International Symposium
language:
Short-container-title:

Author:

Novikov Vladimir V.¹^ORCID,Markelov Vladimir A.¹^ORCID,Shevyakov Alexander Yu.¹^ORCID,Gusev Anatoly Y.¹^ORCID,Linhart Stanislav²^ORCID,Sevecek Martin²^ORCID,Belac Josef²,Rehacek Radomir²,Stary Vladislav²,Shishkin Aleksey A.³,Grekhov Maksim M.³,Pesek Pavel⁴,Fencl Zdenek⁴,Halodova Patricie⁵

Affiliation:

1. SC “VNIINM,” Rogova St., 5A, Moscow, RU 123098

2. ALVEL, a.s., Stefanikova 110/41, Brno, CZ 602 00

3. JSC “TVEL,” Kashirskoe shosse 49, Moscow, RU 115409

4. UJV Řež, Hlavni 130, Husinec-Řež, CZ 250 68

5. Research Centre Řež, Hlavni 130, Husinec-Řež, CZ 250 68

Publisher

ASTM International

Reference10 articles.

1. P. V. Shebaldov, M. M. Peregud, A. V. Nikulina, Y. K. Bibilashvili, A. F. Lositski, N. V. Kuz’menko, V. I. Belov, and A. E. Novoselov, “E110 Alloy Cladding Tube Properties and Their Interrelation with Alloy Structure-Phase Condition and Impurity Content,” in Zirconium in the Nuclear Industry: Twelfth International Symposium, ed. G. P. Sabol and G. D. Moan (West Conshohocken, PA: ASTM International, 2000), 545–557, https://doi.org/10.1520/STP14316S

2. V. N. Shishov, V. A. Markelov, A. V. Nikulina, V. V. Novikov, M. M. Peregud, A. Y. Shevyakov, I. N. Volkova, G. P. Kobylyansky, A. E. Novoselov, and A. V. Obukhov, “Corrosion, Dimensional Stability and Microstructure of VVER-1000 E635 Alloy FA Components at Burnups up to 72 MWday/kgU,” in Zirconium in the Nuclear Industry: 17th Volume, ed. R. J. Comstock and P. Barberis (West Conshohocken, PA: ASTM International, 2015), 628–650, https://doi.org/10.1520/STP154320120146

3. S. Yagnik, R. B. Adamson, G. Kobylyansky, J.-H. Chen, D. Gilbon, S. Ishimoto, T. Fukuda, L. Hallstadius, A. Obukhov, and S. Mahmood, “Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants,” in Zirconium in the Nuclear Industry: 18th International Symposium, ed. R. J. Comstock and A. T. Motta (West Conshohocken, PA: ASTM International, 2018), 748–795, https://doi.org/10.1520/STP159720160040

4. S. Doriot, B. Verhaeghe, J.-L. Béchade, D. Menut, D. Gilbon, J.-P. Mardon, J.-M. Cloue, A. Miquet, and L. Legras, “Microstructural Evolution of M5TM7 Alloy Irradiated in PWRs up to High Fluences—Comparison with Other Zr-Based Alloys,” in Zirconium in the Nuclear Industry: 17th Volume, ed. R. J. Comstock, and P. Barberis (West Conshohocken, PA: ASTM International, 2015), 759–799, https://doi.org/10.1520/STP154320120179

5. V. N. Shishov, “The Evolution on Microstructure and Deformation Stability in Zr-Nb-(Sn,Fe) Alloys under Neutron Irradiation,” in Zirconium in the Nuclear Industry: 16th International Symposium, ed. P. Barberis and M. Limback (West Conshohocken, PA: ASTM International, 2012), 37–66, https://doi.org/10.1520/STP152920120003