The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor
| Autor: | Vojtěch Rypar, Michal Kostal, Vlastimil Juříček, Tomáš Czakoj, Jan Šimon, David Harut, Zdeněk Matěj, František Cvachovec, Martin Schulc, Evžen Losa, Vít Klupák |
|---|---|
| Rok vydání: | 2018 |
| Předmět: |
Materials science
010308 nuclear & particles physics Astrophysics::High Energy Astrophysical Phenomena Nuclear engineering Monte Carlo method Flux Baffle 010403 inorganic & nuclear chemistry 01 natural sciences 7. Clean energy 0104 chemical sciences Reactor operator Nuclear Energy and Engineering Mockup Neutron flux 0103 physical sciences Neutron VVER |
| Zdroj: | Annals of Nuclear Energy. 121:567-576 |
| ISSN: | 0306-4549 |
| DOI: | 10.1016/j.anucene.2018.08.007 |
| Popis: | The neutron flux distribution in the internal parts of a reactor is an important parameter which affects the absorbed dose, temperature, and gas production in the materials. Therefore, the knowledge of neutron flux distribution, for example in the baffle, is important for estimation of the radiation-induced swelling and activation of this internal component. The power distribution in the periphery fuel assemblies, mostly the lateral 2–3 pin rows, has considerable influence on neutron and gamma flux in the internal reactor elements. The power distribution in the core is mostly calculated by the reactor operator using diffusion codes. These data are used as an input for transport calculations, e.g., with Monte Carlo for the fluences, displacements per atoms, gamma heating and other important values for radiation damage estimation. This paper aims to compare the experimental and calculated reaction rate distribution in a mock-up of VVER-1000 (VVER-1000 Mock-Up) internals placed in the LR- 0 reactor and compares these quantities in case of a partial change of enrichment in one fuel assembly adjacent to the baffle simulator. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full Text from ScienceDirect