Modelling of the spatial distribution of the induced activities in the RBMK-1500 reactor graphite blocks and rings/sleeves |
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| Affiliation: | 1. Southwest University of Science and Technology, Mianyang, Sichuan 621010, China;2. College of Science, National University of Defense Technology, Changsha, Hunan 410073, China;3. University of Science and Technology of China, Hefei, Anhui 230027, China;4. Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan 621900, China;1. Traffic College, Northeast Forestry University, 150040, China;2. Department of Computing, Engineering, and Technology, Faulty of Applied Siences, University of Sunderland, Sunderland, SR6 0DD, UK;3. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China;1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan RD. Minhang District, Shanghai, China;2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China;1. Kyung Hee Univ., Yongin-si, Gyeonggi-do, 446-701, Republic of Korea;2. KEPCO International Nuclear Graduate School(KINGS), Ulsan, Republic of Korea |
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| Abstract: | There is one nuclear power plant (NPP) in Lithuania – the Ignalina NPP – which is under decommissioning now. The Ignalina NPP has two units with RBMK-1500 reactors, which are the most powerful and the most advanced versions of RBMK-type reactor design. Unit 1 of the Ignalina NPP was shut down at the end of 2004 and Unit 2 was shut down at the end of 2009. RBMK is a water-cooled graphite-moderated channel-type power reactor and the decommissioning of these reactors faces specific challenges for proper characterisation and disposal of irradiated reactor graphite.Apart from radiological inventory, the spatial distribution of radionuclides in the reactor graphite is also very important because it could indicate the possibilities for decontamination/treatment of the irradiated graphite. This is important for consideration of the near surface disposal option for irradiated graphite, as without treatment it usually does not meet the waste acceptance criteria.Based on that, the work presented in this paper is focused on the modelling of the induced activity spatial distribution in the Ignalina NPP RBMK-1500 reactor graphite components: blocks and rings/sleeves. The modelling was performed with MCNP and SCALE computer codes and consisted of two mains stages: modelling of the neutron flux in the reactor graphite components, and then modelling of the neutron activation in them using the already modelled neutron flux. In such a way, the spatial induced activity distribution in the analysed reactor components was obtained. Modelling results show that the thermal neutron flux is more intensive in the outer radial regions of the graphite components and this, in general, results in higher induced activities there. |
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| Keywords: | Reactor RBMK-1500 Irradiated graphite Neutron activation |
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