Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Occupational radiation exposure control analyses of 14 MeV neutron generator facility: A neutronic assessment for the biological and local shield design

  • Swami, H.L. (Institute for Plasma Research) ;
  • Vala, S. (Institute for Plasma Research) ;
  • Abhangi, M. (Institute for Plasma Research) ;
  • Kumar, Ratnesh (Institute for Plasma Research) ;
  • Danani, C. (Institute for Plasma Research) ;
  • Kumar, R. (Institute for Plasma Research) ;
  • Srinivasan, R. (Institute for Plasma Research)
  • Received : 2019.06.03
  • Accepted : 2020.01.08
  • Published : 2020.08.25
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Abstract

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 -VII 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.

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References

  1. R. Srinivasan, et al., Strategy for the Indian DEMO design, Fusion Eng. Des. 83 (2008) 889-892. https://doi.org/10.1016/j.fusengdes.2008.07.038
  2. Shishir Deshpande, Kaw Predhiman, Fusion research programme in India, Part 5, Sadhana 38 (October 2013) 839-848. https://doi.org/10.1007/s12046-013-0166-9
  3. R. Srinivasan, The Indian DEMO Team Role of fusion energy in India, J. Plasma Fusion Res. Ser. 9 (2010) 630-634.
  4. R. Srinivasan, Design and analysis of SST-2 fusion reactor, Fusion Eng. Des. 112 (2016) 240-243. https://doi.org/10.1016/j.fusengdes.2015.12.044
  5. E. Rajendra Kumar, et al., Overview of TBM R&D activities in India, Fusion Eng. Des. 87 (2012) 461-465. https://doi.org/10.1016/j.fusengdes.2011.12.014
  6. H.L. Swami, et al., Activation characteristics of candidate structural materials for a near-term Indian fusion reactor and the impact of their impurities on design considerations, Plasma Sci. Technol. 20 (2018), 065602. https://doi.org/10.1088/2058-6272/aaabb4
  7. Paritosh Chaudhuri, et al., Progress in engineering design of Indian LLCB TBM set for testing in ITER, October (7-8), Fusion Eng. Des. 89 (2014) 1362-1369. https://doi.org/10.1016/j.fusengdes.2014.02.001
  8. H.L. Swami, et al., Neutronic performance of Indian LLCB TBM set conceptual design in ITER, Fusion Eng. Des. 113 (2016) 71-81. https://doi.org/10.1016/j.fusengdes.2016.09.012
  9. M. Angelone, et al., Neutronic experiment on a mockup of the ITER shielding system at the Frascati Neutron Generator, Fusion Eng. Des. 42 (1998) 255-260. https://doi.org/10.1016/S0920-3796(97)00169-5
  10. Shrichand Jakhar, et al., Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons, Fusion Eng. Des. 95 (2015) 50-58. https://doi.org/10.1016/j.fusengdes.2015.04.003
  11. H.L. Swami, et al., A neutronic experiment to support the design of Indian TBM shield module for ITER, Plasma Sci. Technol. (2019), https://doi.org/10.1088/2058-6272/ab079a.
  12. Sudhirsinh Vala, et al., Rotating tritium target for intense 14-MeV neutron source, Fusion Eng. Des. 123 (2017) 77-81. https://doi.org/10.1016/j.fusengdes.2017.05.117
  13. R. Makwana, et al., Shielding design of the proposed laboratory for intense 14 MeV neutron generator, Indian J. Pure Appl. Phys. 50 (2012) 799-801.
  14. AERB Directive No. 01/2011, Under Rule 15 of the Atomic Energy (Radiation Protection) Rules, Ref. No. CH/AERB/ITSD/125/2011/1507 dated, 2004, https://aerb.gov.in/english/acts-regulations/safety-directives. (Accessed 27 April 2011).
  15. J.T. Goorley, et al., "Initial MCNP6 Release Overview-MCNP6 Version 1.0," LA-UR-13-22934, Los Alamos National Laboratory, 2013.
  16. M.B. Chadwick, P. Oblozinsky, M. Herman, et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets 107 (2006) 2931. https://doi.org/10.1016/j.nds.2006.11.001
  17. ICRP, Conversion coefficients for use in radiological protection against external radiation, ICRP Publication 74, Ann. ICRP 26 (3-4) (1996).
  18. H.L. Swami, et al., Neutronic design optimization of ITER TBM port#2 bioshield plug, Fusion Eng. Des. 137 (2018) 49-55. https://doi.org/10.1016/j.fusengdes.2018.08.015
  19. D. Leichtle, et al., Status of the ITER tokamak nuclear shielding and radiological protection design, Fusion Eng. Des. 109-111 (2016) 666-672. https://doi.org/10.1016/j.fusengdes.2016.02.023

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