Zobrazeno 1 - 10
of 14
pro vyhledávání: '"MM Peregud"'
Publikováno v:
Voprosy Materialovedeniya. :206-212
Modified zirconium alloys E635Mand E635opt based on E635 alloy (E635 was selected as master alloy) have been developed at Bochvar Institute. Fuel rods with such claddings were manufactured at Bochvar Institute and were irradiated at MIR reactor (SC R
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3300217aedd5a7b6769abe80d802afa9
https://doi.org/10.22349/1994-6716-2018-95-3-206-212
https://doi.org/10.22349/1994-6716-2018-95-3-206-212
Autor:
A. A. Kosaurov, V. A. Ovchinnikov, A. A. Shel’dyakov, A. B. Nikulina, G. V. Kulakov, MM Peregud, V. Yu. Shishin, Yu. V. Konovalov
Publikováno v:
Atomic Energy. 123:399-405
The first reactor tests and post-reactor studies of fuel elements with cladding made from the zirconium alloys E-636M, E-635opt, and E-635M1, developed at VNIINM, have been conducted. The purpose of the studies was to search for alloys of the type E-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::766edae1029224ff58218a412e0d3390
https://doi.org/10.1007/s10512-018-0359-8
https://doi.org/10.1007/s10512-018-0359-8
Publikováno v:
Atomic Energy. 123:235-243
The dependence of dimensional changes occurring in the structural parts made of E-635 zirconium alloy on the metallurgical and operational factors as a result of thermal creep, radiation growth, and radiation creep was studied. Tests close to operati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2cbd9b1fcef44ac9baf637bd2dfe9155
https://doi.org/10.1007/s10512-018-0332-6
https://doi.org/10.1007/s10512-018-0332-6
Autor:
MM Peregud, G. V. Kulakov, A. A. Kosaurov, Yu. V. Konovalov, A. A. Shel’dyakov, E. A. Korotchenko, A. V. Vatulin, V. Yu. Shishin
Publikováno v:
Atomic Energy. 122:87-92
The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that reorientation of zirconium hydrides can occur in fuel-element cladding under the action of ten
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6c5b0b6f33caffe61007cb6ab5125f10
https://doi.org/10.1007/s10512-017-0240-1
https://doi.org/10.1007/s10512-017-0240-1
Autor:
V. Markelov, GP Kobylyansky, AE Novoselov, A. V. Nikulina, I. Volkova, VN Shishov, A. V. Obukhov, A. Shevyakov, V. Novikov, MM Peregud
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f0f07ce33f0afdf6547406cf2bc38d9d
https://doi.org/10.1520/stp154320120146
https://doi.org/10.1520/stp154320120146
Publikováno v:
Journal of Nuclear Materials. 238:205-210
The high resistance to nodular corrosion and irradiation-induced creep and growth shown by Zr-1% Sn-1% Nb-0.4% Fe compared with Zircaloy or binary Zr Nb alloys requires a scientific explanation of the alloy's irradiation stability through analysis of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42a511a1e22bffc7b85831da27070d93
https://doi.org/10.1016/s0022-3115(96)00453-9
https://doi.org/10.1016/s0022-3115(96)00453-9
Zirconium Alloy E635 as a Material for Fuel Rod Cladding and Other Components of VVER and RBMK Cores
Autor:
MM Peregud, GP Kobylyansky, VA Kotrekhov, AV Nikulina, AE Novoselov, NV Kuz'menko, AF Lositsky, VK Shamardin, Yu. P. Shevnin, V. A. Markelov, YK Bibilashvili
Data are given on Zr alloy E635 (Zr-1.2Sn-1Nb-0.4Fe), developed in Russia as a fuel rod cladding and other component material for use in cores of VVER and RBMK types. The alloy is much superior to binary alloys with 1.0 and 2.5% Nb and Zircaloys in t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7973f116494cc47b6cbfdea9c63bbeed
https://doi.org/10.1520/stp16201s
https://doi.org/10.1520/stp16201s
Zirconium alloy components subjected to long-term operation and high doses in thermal reactors need to be highly irradiation resistant to provide integrity of components, primarily, their geometrical sizes. Transmission and scanning electron microsco
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4f0668d58f6b29bf6fcb5937de50e64
https://doi.org/10.1520/stp13919s
https://doi.org/10.1520/stp13919s
Autor:
VN Shishov, AV Kozlov, AV Nikulina, MM Peregud, V. A. Markelov, SA Kolbenkov, AE Novoselov, S. A. Averin
Studied were evolution of dislocation structure, phase, and element composition of binary alloys Zr-1Nb and Zr-2.5Nb and multicomponent alloys Zr-1Nb-1.2Sn-0.4Fe and Zr-1.25n-0.4Fe under neutron irradiation. The investigations were carried out using
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::527879f6c44205aa2dabc14b386b7821
https://doi.org/10.1520/stp16192s
https://doi.org/10.1520/stp16192s