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[en] The technique for determination of the powder gas permeability is proposed, and the model for calculation of pressure time variation through the height of an absorber rod is developed. It is shown that the model application permits to make the justified estimation of 10 B burnup and hence the probability of absorber element failure under the impact of gas release inside the can
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. 36-39; Methodological provisions of reactor materials testing; Metodicheskoe obespechenie reaktornogo materialovedeniya; Dimitrovgrad (Russian Federation); 30-31 Mar 1999; 1 fig.
; 1999; p. 36-39; Methodological provisions of reactor materials testing; Metodicheskoe obespechenie reaktornogo materialovedeniya; Dimitrovgrad (Russian Federation); 30-31 Mar 1999; 1 fig.
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. 59-60; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 59-60; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
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. 59; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 59; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
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
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. 57; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 57; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
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. 145; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 145; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
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. 144; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
; 1997; p. 144; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
[en] In a SM reactor the tests are carried out for absorber member mockup containing B4C boron carbide powder and pellets with a natural content of 10B and with claddings of alloy EhP-630U or steels SS316L and SS304L. The tests simulate a hypothetical situation in a WWER-1000 type reactor in the event that the coolant supply is cut off or reduced. The testing results shown that the change of EhP630U dimensions and clad leakage take place due to boron carbide swelling and gas release out of the core of absorbed element under radiation and high temperature effects. Unsealed absorber element mockups hold their dimensions and shape. It is concluded that unsealed clads in an absorber member design are able to enhance the operational capability
[ru]
В реакторе СМ проведены испытания макетов поглощающих элементов с порошком и таблетками карбида бора В4С с природным содержанием 10В и оболочкой из сплава ЭП-630У или сталей SS316L и SS304L. Проведенные испытания имитируют гипотетическую ситуацию, которая может возникнуть в реакторе ВВЭР-1000 в случае прекращения или уменьшения подачи теплоносителя. Результаты испытаний показали, что в результате распухания карбида бора и газовыделения из сердечника под влиянием облучения и высокой температуры произошло изменение размеров оболочки из сплава ЭП-630У и ее разгерметизация. Негерметичные конструкции макетов пэлов сохранили геометрические размеры и форму. Сделан вывод, что негерметичность оболочки в конструкции поглощающего элемента способна повысить его работоспособностьSource
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 355 p; ISBN 5-85165-651-4; ; 2001; p. 326-339; 6. Russian conference on reactor material science; Shestaya Rossijskaya konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 11-15 Sep 2000; 7 figs., 4 tabs.
; 2001; p. 326-339; 6. Russian conference on reactor material science; Shestaya Rossijskaya konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 11-15 Sep 2000; 7 figs., 4 tabs.
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