Development and use of the IVV-2M fuel assembly
| Autor: | V. E. Pivovarov, I. A. Stenbok, V. I. Zelenov, Yu. A. Safin, S. G. Karpechko, V. D. Zaboikin, Yu. M. Bulkin, V. G. Aden, E. F. Kartashev, A. G. Sila-Novitskii, V. I. Uvarov, I. Ya. Emel'yanov, A. D. Nikiforov, Ya. D. Pakhomov, A. S. Terekhov, V. I. Vasenkov |
|---|---|
| Rok vydání: | 1986 |
| Předmět: |
Materials science
Nuclear engineering Uranium dioxide General Engineering Solid fuel Neutron temperature Nuclear physics Condensed Matter::Materials Science chemistry.chemical_compound Nuclear Energy and Engineering Nuclear reactor core chemistry Neutron flux visual_art Aluminium alloy visual_art.visual_art_medium Research reactor Physics::Chemical Physics Burnup |
| Zdroj: | Soviet Atomic Energy. 61:902-906 |
| ISSN: | 1573-8205 0038-531X |
| Popis: | The design and performance of a fuel assembly, intended for use in the water cooled and moderated IVV-2M research reactor and consisting of dioxide dispersed in an aluminium alloy matrix encased in an aluminium alloy can, is presented. Experimental and theoretical studies included neutron characteristics of the reactor core, thermohydraulic behavior, and thermal neutron flux distribution. Data are also presented on the specific charge in u 235, the metal to water volume ratio, the specific heat removal surface, and maximum power of the assembly. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full text from SpringerLink