| 1. |
- Asmolov, V.G., et al.
(författare)
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Partitioning of Zr, U and FP between Molten Oxidic and Metallic Corium
- 2004
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Ingår i: Proceeding of MASCA Seminar.
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Konferensbidrag (refereegranskat)abstract
- Interaction of molten corium and liquid iron/stainless steel has been studied in different tests of theMASCA-1 program. These tests utilized the technology of induction melting in a cold crucible. Themasses of tested corium were approximately 0.5, 2 and 100 kg. Representative quantities of Mo, Ru,SrO, BaO, CeO2 and La2O3 served as fission product simulants.After the suboxidized melt - steel interaction U and Zr have been found in the metallic phase.To quantify the partitioning of Zr, U and fission products an extensive experimental program has beenperformed. The following key parameters have been identified: oxygen potential in the melt (degree ofZr-oxidation), the corium/steel mass ratio and U/Zr ratio. The paper discusses the influence of theseparameters on the partitioning of the main species.
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| 2. |
- Bechta, Sevostian, et al.
(författare)
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Experimental studies of oxidic molten corium-vessel steel interaction
- 2001
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Ingår i: Nuclear Engineering and Design. - 0029-5493 .- 1872-759X. ; 210:1-3, s. 193-224
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Tidskriftsartikel (refereegranskat)abstract
- The experimental results of molten corium-steel specimen interaction with molten corium on the 'Rasplav-2' test facility are presented. In the experiments, cooled vessel steel specimens positioned on the molten pool bottom and uncooled ones lowered into the molten pool were tested. Interaction processes were studied for different corium compositions, melt superheating and in alternative (inert and air) overlying atmosphere. Hypotheses were put forward explaining the observed phenomena and interaction mechanisms. The studies presented in the paper were aimed at the detection of different corium-steel interaction mechanisms. Therefore certain identified phenomena are more typical of the ex-vessel localization conditions than of the in-vessel corium retention. Primarily, this can be referred to the phenomena of low-temperature molten corium-vessel steel interaction in oxidizing atmosphere.
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| 3. |
- Bechta, Sevostian, et al.
(författare)
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New experimental results on the interaction of molten corium with reactor vessel steel
- 2004
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Ingår i: Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04. - : American Nuclear Society. - 0894486802 ; , s. 1072-1081
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Konferensbidrag (refereegranskat)abstract
- In order to justify the concept of in-vessel core melt retention, it is necessary to understand the thermal and physico-chemical phenomena. Especially the interaction of the molten pool with the reactor vessel during outside cooling needs to be understood. These phenomena are very complex, in particular, where interactions with the oxidic melt are concerned. In the early stages of the retention process, the oxidic corium and the vessel steel interact under the conditions of low oxygen potential in the melt. These conditions can be simulated by a molten corium having the composition UO2/ZrO 2Zr, where the degree of Zr-oxidation is in the range between 30 % (C-30) and 100 % (C-100). Corresponding experiments with prototypic melts at low oxygen potentials are being performed in the ISTC METCOR project 2nd phase. These are: MC 5 of corium composition 71w%UO2-29w%ZrO 2 (C-100) in neutral atmosphere (argon), MC 6 of corium composition 76w%UO2-9w%ZrO2-15w%Zr (C∼30), also in argon. In test MC 5, the interaction of molten C-100 corium with a water-cooled steel specimen was studied for the following maximum temperatures at the specimen surface: 1075°C, 1180°C, 1315°C and 1435°C. The total duration of the experiment was ∼ 36 hours. The MC5 test serves as a reference test for determining the characteristics of the interaction between oxidic melt and steel specimen under the conditions of minimum chemical interaction potential. To investigate the effect of substoichiometry, test MC 6 was then performed with suboxidized molten corium C∼30. The maximum surface temperature of the cooled steel specimen was held at ∼ 1400°C. The test duration was ∼ 10 hours. The ablation phenomena were found to differ significantly from those observed both in the reference test, as well as in former tests with oxidized melts, as they involved the formation of a low-melting metallic phase at the interface which contains iron, zirconium and uranium. The paper summarizes the results of the experiments and of the performed posttest analysis for tests MC 5 and MC 6.
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| 4. |
- Bechta, Sevostian, et al.
(författare)
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Water boiling on the corium melt surface under VVER severe accident conditions
- 2000
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Ingår i: Nuclear Engineering and Design. - 0029-5493 .- 1872-759X. ; 195:1, s. 45-56
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Tidskriftsartikel (refereegranskat)abstract
- Experimental results are presented on the interaction of corium melt with water supplied on its surface. The tests were conducted in the `Rasplav-2' experimental facility. Corium melt was generated by induction melting in the cold crucible. The following data were obtained: heat transfer at boiling water-melt surface interaction, gas and aerosol release, post-interaction solidified corium structure. The corium melt charge had the following composition, mass%: 60% UO2+x-16% ZRO2-15% Fe2O3-6% Cr2O3-3% Ni2O3. The melt surface temperature ranged within 1920-1970 K.
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| 5. |
- Gusarov, V.V., et al.
(författare)
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Method for producing ceramic materials incorporating ferric oxide, alumina, and silicon dioxide for nuclear-reactor molten core trap
- 2002
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Patent (populärvet., debatt m.m.)abstract
- NOVELTY - Production of ceramic materials for nuclear reactor molten core trap involves preparation of charge by milling and mixing components, and producing molding powder from charge. This molding powder is molded and formed into briquettes, which are calcined in an air environment at 1300 - 1380 degreesC for 2-14 hr. The briquettes are crushed, the powder is milled and sized to fractions, and mixed with binder. The parts are molded and calcined at 1200-1300 degreesC for 4-14 hr. Silicon dioxide and part of the alumina are introduced into the charge as kaolin, whose content is higher than the desired content of silicon dioxide in material by 2.1-2.3 times. USE - In nuclear power engineering, for confining molten core in water-cooled tank reactors. ADVANTAGE - Enhanced reproducibility of physical and mechanical properties of molten core sacrificial ceramic materials.
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| 6. |
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| 7. |
- Gusarov, V.V., et al.
(författare)
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Oxidic material for nuclear reactor core melt catcher
- 2001
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Patent (populärvet., debatt m.m.)abstract
- NOVELTY - Oxide material of molten core catcher incorporating Al2O3,SiO2, also contains Fe2O3 and/or Fe3O4, and target dopant of one or more oxides of following group: SrO,CeO2,BaO,Y2O3,La2O3. Proportion of ingredients is, in mass percent: Fe2O3 and/or Fe3O4, 46-80; Al2O3, 16-50; SiO2, 1-4; target dopant, 3-15. The material has content of radioactive strontium and cerium isotopes in gas phase above molten core that is reduced by 2-7 times. USE - For nuclear reactor molten core catcher. ADVANTAGE - Reduced radioactivity of molten core.
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| 8. |
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| 9. |
- Gusarov, V.V., et al.
(författare)
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Oxidmaterial for fallan av en karnreaktors smalt mantel
- 2001
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Patent (populärvet., debatt m.m.)abstract
- The inventive oxide material for a molten-core catcher of a nuclear reactor comprises Fe>23< and /or Fe>34< and Al>23<. The content of Al>23< and /or Fe>34 23 <%. Said material can also contain up to 4 mass % of SiO2, preferably from 1 to 4 mass %. The material can be embodied in the form of a ceramic material or concrete which additionally contains up to 20 mass % of cement binder.; The inventive oxide material for a molten-core catcher of a nuclear reactor comprises Fe2O3 and /or Fe3O4 and Al2O3. The content of Al2O3 and /or Fe3O4 ranges from 46 to 80 mass %, and Al2O3 from 16 to 50 mass %. Said material can also contain up to 4 mass % of SiO2, preferably from 1 to 4 mass %. The material can be embodied in the form of a ceramic material or concrete which additionally contains up to 20 mass % of cement binder.
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| 10. |
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| 11. |
- Khabensky, V.B., et al.
(författare)
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System for localization and cooling of corium of accidental light water nuclear reactor
- 2003
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Patent (populärvet., debatt m.m.)abstract
- FIELD: systems for localization and cooling of melted body at emergency its exit for the limits of the reactor's body. ^ SUBSTANCE: cooling trap is located in the mine under the reactor and fulfilled in the form of a vessel with installed in it a basket with sacrificial materials-diluters of uranium containing and steel components of corium. The bottom of the cooling drum is no less than on 30% thicker of its walls and has an incline to the center in the limits of 10-20 degrees; sacrificial materials-diluters are formed in the shape of briquettes enclosed in the steel drum. The mass of the material-diluters of oxide uranium containing and steel components of corium are determined with the help of calculated ratio computations which take into considerations: the mass of components of the corium, incoming from the reactor; physical parameters of components of melt; density of critical thermal flow drawing off the melts to cooling water through the drum. It is proposed to fulfill the directing arrangement for the body in the form of a funnel located between the bottom of the reactor and the higher edge of the trap. At that the walls of the directing arrangement are covered with heat-resistant concrete, over which a covering of easily melted concrete is put on. ^ EFFECT: the invention allows to increase efficiency and reliability of the system by way of improving conditions for coming in and cooling of melted corium in the trap. ^ 4 cl, 1 dwg
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