Occupational radiation exposure control analyses of 14?MeV neutron generator facility: A neutronic assessment for the biological and local shield design

Swami H.L.; Vala S.; Abhangi M.; Kumar Ratnesh; Danani C.; Kumar R.; Srinivasan R.

doi:10.1016/j.net.2020.01.006

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자료유형: 학술저널

저자정보: Swami H.L. (a Institute for Plasma Research, Gandhinagar) Vala S. (a Institute for Plasma Research, Gandhinagar) Abhangi M. (a Institute for Plasma Research, Gandhinagar) Kumar Ratnesh (a Institute for Plasma Research, Gandhinagar) Danani C. (a Institute for Plasma Research, Gandhinagar) Kumar R. (a Institute for Plasma Research, Gandhinagar) Srinivasan R. (a Institute for Plasma Research, Gandhinagar)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제8호

발행연도: 2020.8

수록면: 1,784 - 1,791 (8page)

DOI: 10.1016/j.net.2020.01.006

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The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct the lab scale experiments related to Indian breeding blanket system for ITER and DEMO. It will also be utilized for material testing, shielding experiments and development of fusion diagnostics. Occupational radiation exposure control is necessary for the all kind of nuclear facilities to get the operational licensing from governing authorities and nuclear regulatory bodies. In the same way, the radiation exposure for the 14 MeV neutron generator facility at the occupational worker area and accessible zones for general workers should be under the permissible limit of AERB India. The generator is designed for the yield of 1012 n/s. The shielding assessment has been made to estimate the radiation dose during the operational time of the neutron generator. The facility has many utilities and constraints like ventilation ducts, accessible doors, accessibility of neutron generator components and to conduct the experiments which make the shielding assessment challenging to provide proper safety for occupational workers and the general public. The neutron and gamma dose rates have been estimated using the MCNP radiation transport code and ENDF eVII nuclear data libraries. The ICRP-74 fluence to dose conversion coefficients has been used for the assessment. The annual radiation exposure has been assessed by considering 500 h per year operational time. The provision of local shield near to neutron generator has been also evaluated to reduce the annual radiation doses. The comprehensive results of radiation shielding capability of neutron generator building and local shield design have been presented in the paper along with detailed maps of radiation field

#Neutron generator #Shielding #MCNP #Dose rat

참고문헌 (19)

참고문헌 신청

R. Srinivasan / 2008 / Strategy for the Indian DEMO design / Fusion Eng. Des 83:889~892

Shishir Deshpande / 2013 / Fusion research programme in India, Part 5 / Sadhana 38:839~848

R. Srinivasan / 2010 / The Indian DEMO Team Role of fusion energy in India / J. Plasma Fusion Res. Ser 9:630~634

R. Srinivasan / 2016 / Design and analysis of SST-2 fusion reactor / Fusion Eng. Des 112:240~243

E. Rajendra Kumar / 2012 / Overview of TBM R&D activities in India / Fusion Eng. Des 87:461~465

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