The research of the ceramic fuel pins, irradiated in the technological channels of the ATS of IVG.1 reactor
Deryavko, I.I.; Kolodeshnikov, A.A.; Pivovarov, O.S.; Storozhenko, A.N.
Abstracts of 4.International conference 'Nuclear and Radiation Physics'2003
Abstracts of 4.International conference 'Nuclear and Radiation Physics'2003
AbstractAbstract
[en] The basic objective of the work is to install the qualitative and quantitative indexes of the serviceability of the rod-type carbide fuel pins as applied to the exploitation conditions in the high temperature gas cooled reactor, where the nitrogen will be used as the coolant. For that purpose the state of the fuel pins, tested in the nitrogen technological channels of the ATS of IVG.1 (EWG-1) reactor in the series of four research nitrogen start-ups , including the energetic start-up with the duration of 160 s. and three standard start-ups with the duration of 510 s., was researched. On the base of the results of the post-reactor research of the fuel pins of ten channels of ATS it is determined that the ceramic fuel pins of (U, Zr)C+C, (U, Nb)C+C and (U, Zr,Nb)C are enough serviceable in the severe conditions of the high temperature tests in the flow path of the chemically aggressive coolant. The lack of the surface cracks in the fuel pins, lack of the fuel pins failures and lack of overweight and thickening of the fuel pins are revealed. It is observed the oxy-nitration of the fuel pins surfaces (at appearance of the characteristic color tones and presence of the slight burning of the fuel rods to each other), however, the depth of the oxy-nitration , even of the fuel pins of the output heating sections, tested at 2800 K, did not exceed 10 μm. It is found out that the levels of the radioactive change of the fuel pins parameters are the same as of the fuel pins of the hydrogen technological channels, tested at the same temperatures and up to the same neutrons fluences. The low change of the fuel pins strength is observed; the strengthening of the fuel pins on the output heating sections for ∼ 20 % (due to the appearance of the residual radiation macro stresses) and weakening of the fuel pins in the output sections for ∼30 % (due to oxy-nitration and erosion of the surface, and also non-congruent evaporating of the surface material). The prognostic analysis of the fuel pins behavior in the case of the increase of the number of the reactor start-ups from 4 to the reserve 40 and duration of the tests from ∼700 s to reverse 5000 s is made. It is shown that their strength can reduce under the influence of the oxy-nitration, erosion, evaporating, corrosion under the pressure and tiredness of the vibrational load down to hazardous low level. That's why the first principal decision of the problem of increasing the serviceability of the ceramic fuel pins in the nitrogen - cooled channels is to change the carbide fuel pins to the carbonitride ones. The second decision of the problem is to remove the curling of the bundles of the fuel pins in the heating sections. In that case the favourable situation is created, in which the maximal depth of the fuel pins oxy-nitration will be of the principal value, and this value, according to the design estimations, is not to exceed 30 μm by the end of the full-resource tests. Taking into account this fact, the conclusion of the possibility to use the rod carbide fuel pins in the nitrogen cooled reactor without changing their material composition is made
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Source
Ministerstvo Ehnergetiki i Mineral'nykh Resursov Respubliki Kazakhstan, Astana (Kazakhstan); Natsional'nyj Yadernyj Tsentr Respubliki Kazakhstan, Kurchatov (Kazakhstan); Natsional'naya Akademiya Nauk Respubliki Kazakhstan, Almaty (Kazakhstan); Inst. Yadernoj Fiziki Natsional'nogo Yadernogoj Tsentra Respubliki Kazakhstan, Almaty (Kazakhstan); Yadernoe Obshchestvo Respubliki Kazakhstan, Almaty (Kazakhstan); 513 p; ISBN 9965-675-01-5; ; 2003; p. 234-235; 4.International conference 'Nuclear and Radiation Physics'; 4.Mezhdunarodnaya konferentsiya 'Yadernaya i Radiatsionnaya Fizika'; Almaty (Kazakhstan); 15-17 Sep 2003
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Book
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Conference
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Descriptors (DEI)
Descriptors (DEC)
BERYLLIUM MODERATED REACTORS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUEL ELEMENTS, FUELS, GAS COOLED REACTORS, IRRADIATION REACTORS, MATERIALS, MATERIALS TESTING REACTORS, METAL MODERATED REACTORS, NUCLEAR FUELS, OPERATION, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SOLID FUELS, TANK TYPE REACTORS, TEMPERATURE RANGE, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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