Методика параметричного опису вхідних даних для розрахунку радіаційного розпухання внутрішньокорпусних пристроїв ВВЕР-1000
Ukraine currently does not have a company to perform full neutronic calculations of VVER-1000 core. In this regard, the paper proposes a method of parametric assignment of volumetric heating due to gamma-radiation and the irradiation dose rate in VVER-1000 core baffle. The method significantly simpl...
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| Date: | 2016 |
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| Main Authors: | , |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2016
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/31 |
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| Journal Title: | Nuclear and Radiation Safety |
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Nuclear and Radiation Safety| Summary: | Ukraine currently does not have a company to perform full neutronic calculations of VVER-1000 core. In this regard, the paper proposes a method of parametric assignment of volumetric heating due to gamma-radiation and the irradiation dose rate in VVER-1000 core baffle. The method significantly simplifies assessment of the stationary temperature, irradiation swelling and stress-strain state of pressure vessel internals. The method is based on the approximation of the input fields by polynomial s of nth degree in the radial and circumferential coordinates. Methodical error in the calculation of the stationary temperature field is 3,2 %, 12,7 % — in the calculation of radiation swelling, 33,0 % — in the evaluation of radial deformations of the core baffle. This allows to use the method for the preliminary assessment of technical condition of the VVER-1000 reactor internals. |
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