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No abstract available
Source
Dimitrovgradskij Nauchnyj Tsentr Povolzhskogo Otdeleniya Akademii Tekhnologicheskikh Nauk Rossijskoj Federatsii, Dimitrovgrad (Russian Federation); 426 p; ISBN 5-94831-013-2; 
; 2002; p. 74-76; 4 refs., 1fig.
; 2002; p. 74-76; 4 refs., 1fig.
[en] The gas extraction facility and technique for mass spectroscopic analysis of the gaseous phase composition developed for experimental determination of helium concentration in irradiated structural materials are described. It is shown that both the facility and technique are successfully applicable when analyzing the content of 4 He isotope in specimens of the stainless steel SS 316 irradiated in the SM reactor. The range of helium concentration measurement is from 1 up to 500 appm
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Koordinatsionnyj nauchno-tekhnicheskij sovet Reaktornoe materialovedenie, Moscow (Russian Federation); Gosudarstvennyj nauchnyj tsentr Rossijskoj Federatsii Nauchno-issledovatel'skij institut atomnykh reaktorov, Dimitrovgrad (Russian Federation); 99 p; ISBN 5-85165-373-6; ; 1999; p. 25-26; Methodological provisions of reactor materials testing; Metodicheskoe obespechenie reaktornogo materialovedeniya; Dimitrovgrad (Russian Federation); 30-31 Mar 1999; 3 refs.
; 1999; p. 25-26; Methodological provisions of reactor materials testing; Metodicheskoe obespechenie reaktornogo materialovedeniya; Dimitrovgrad (Russian Federation); 30-31 Mar 1999; 3 refs.
No abstract available
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Koordinatsionnyj Nauchno-Tekhnicheskij Sovet po Reaktornomu Materialovedeniyu, Moscow (Russian Federation); 60 p; ISBN 5-85165-649-2; ; 2000; p. 14-16; Physical simulation of changing in reactor materials properties under normal and emergency conditions; Fizicheskoe modelirovanie izmeneniya svojstv reaktornykh materialov v nominal'nykh i avarijnykh usloviyakh; Troitsk (Russian Federation); 24-25 Apr 2000; 3 refs., 2 figs., 1 tab.
; 2000; p. 14-16; Physical simulation of changing in reactor materials properties under normal and emergency conditions; Fizicheskoe modelirovanie izmeneniya svojstv reaktornykh materialov v nominal'nykh i avarijnykh usloviyakh; Troitsk (Russian Federation); 24-25 Apr 2000; 3 refs., 2 figs., 1 tab.
No abstract available
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 166 p; ISBN 5-85165-354-X; ; 1997; p. 61; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 61; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
No abstract available
Source
AO «Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii — Fiziko-Ehnergeticheskij Inst. imeni A.I. Lejpunskogo», Obninsk (Russian Federation); 108 p; ISBN 978-5-907108-18-9; ; 2019; p. 83; Scientific-technical conference ''Neutron-physical problems of atomic energy''; Nauchno-tekhnicheskaya konferentsiya «Nejtronno-fizicheskie problemy atomnoj ehnergetiki»; Obninsk (Russian Federation); 27-29 Nov 2019
; 2019; p. 83; Scientific-technical conference ''Neutron-physical problems of atomic energy''; Nauchno-tekhnicheskaya konferentsiya «Nejtronno-fizicheskie problemy atomnoj ehnergetiki»; Obninsk (Russian Federation); 27-29 Nov 2019
[en] Accumulation of radiogenic helium isotope 4He, its diffusion characteristics, and microstructure of beryllium have been studied after irradiation at 70 and 200 deg C by neutrons with an energy of E > 0.1 MeV to fluences of (1.0-13.3) x 1022 cm-2. Experimental results concerning the concentration of radiogenic helium in beryllium after irradiation and subsequent isothermal annealings for 1 h in a temperature range of 700-1200 deg C have been obtained. The accumulation of helium corresponds to a linear dependence up to a neutron fluence of ∼6 x 1022 cm-2 (E > 0.1 MeV); at fluences from 6 x 1022 to 13 x 1022 cm-2 (E > 0.1 MeV), a deviation from the linear dependence toward the decrease in the rate of accumulation is observed. The diffusion of radiogenic helium in beryllium at annealing temperatures of 70-200 deg C is low; intense diffusion and degassing of helium from beryllium start at an annealing temperature of 700 deg C. At annealing temperatures of 1100-1200 deg C, virtually all helium escapes from the irradiated beryllium
[ru]
Проведены исследования процесса накопления радиогенного изотопа гелия 4Не в бериллии, его диффузионных характеристик и микроструктуры бериллия после облучения при температурах 70 град С и 200 град С в области флюенсов нейтронов (1.0-13.3)х1022 см-2 (Е > 0.1 МэВ). Получены экспериментальные результаты содержания радиогенного гелия в бериллии после облучения и последующих изотермических отжигов в течение 1 ч в интервале температур 700-1200 град С. Накопление гелия соответствует линейной зависимости до флюенса нейтронов ∼6х1022 см-2 (Е > 0.1 МэВ), в области флюенсов от 6х1022 см-2 до 13х1022 см-2 (Е > 0.1 МэВ) происходит отклонение от линейной зависимости в сторону снижения темпа его накопления. Диффузия радиогенного гелия в бериллии при температурах облучения 70-200 град С низка, интенсивная диффузия и дегазация гелия начинаются с температуры отжига 700 град С. При температурах отжига 1100-1200 град С практически весь гелий уходит из облученного бериллияJournal
No abstract available
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 166 p; ISBN 5-85165-354-X; ; 1997; p. 58; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 58; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
No abstract available
Source
Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); OAO Gosudarstvennyj Nauchnyj Tsentr - Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 203 p; ISBN 978-5-94831-106-7; ; 2009; p. 143; 9. Russian conference on reactor materials; IX Rossijskaya konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 14-18 Sep 2009
; 2009; p. 143; 9. Russian conference on reactor materials; IX Rossijskaya konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 14-18 Sep 2009
No abstract available
Source
Federal'noe Agentstvo po Atomnoj Ehnergii, Moscow (Russian Federation); Federal'noe Gosudarstvennoe Unitarnoe Predpriyatie Opytnoe Konstruktorskoe Byuro GIDROPRESS, Podol'sk, Moskovskaya Obl. (Russian Federation); 121 p; ISBN 978-5-94883-072-8; ; 2007; p. 113; 5. International scientific and technical conference Safety assurance for NPP with WWER; 5-ya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk, Moskovskaya Obl. (Russian Federation); 29 May - 1 Jun 2007
; 2007; p. 113; 5. International scientific and technical conference Safety assurance for NPP with WWER; 5-ya Mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya Obespechenie bezopasnosti AEhS s VVEhR; Podol'sk, Moskovskaya Obl. (Russian Federation); 29 May - 1 Jun 2007
[en] The necessity of prolongation of operating lifetime of the WWER reactors in Russia and Ukraine, PWR reactors in Europe, Japan and America evoked a great number of examinations of radiation phenomena in austenitic steels under irradiation conditions close to those of operation of power reactor in-vessel devices. This paper is devoted to analysis of the examination results of hardening and changing of microstructure characteristic Fe-18Cr-10Ni-Ti steel irradiated in the WWER-1000 reactors at relatively low irradiation temperatures
Journal
Voprosy Atomnoj Nauki i Tekhniki; ISSN 1562-6016; ; (no.6/91); p. 78-81
; (no.6/91); p. 78-81
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