| 1. |
- Asmolov, V.G., et al.
(författare)
-
Partitioning of Zr, U and FP between Molten Oxidic and Metallic Corium
- 2004
-
Ingår i: Proceeding of MASCA Seminar.
-
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.
|
|
| 2. |
- Bechta, Sevostian, et al.
(författare)
-
New experimental results on the interaction of molten corium with reactor vessel steel
- 2004
-
Ingår i: Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04. - : American Nuclear Society. - 0894486802 ; , s. 1072-1081
-
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.
|
|
| 3. |
- Gusarov, V.V., et al.
(författare)
-
Method for producing ceramic materials incorporating ferric oxide, alumina, and silicon dioxide for nuclear-reactor molten core trap
- 2002
-
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.
|
|
| 4. |
- Gusarov, V.V., et al.
(författare)
-
Oxidic material for nuclear reactor core melt catcher
- 2001
-
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.
|
|
| 5. |
- Gusarov, V.V., et al.
(författare)
-
Oxidmaterial for fallan av en karnreaktors smalt mantel
- 2001
-
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.
|
|
