MIGSHIELD: A new model-based interactive point kernel gamma ray shielding package for virtual environment |
Li, Mengkun
(School of Electric Power, South China University of Technology (SCUT))
Xu, Zhihui (State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment) Li, Wei (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China) Yang, Jun (School of Electric Power, South China University of Technology (SCUT)) Yang, Ming (School of Electric Power, South China University of Technology (SCUT)) Lu, Hongxin (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) Dai, Xinyu (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) |
1 | Monte Carlo Team, MCNP-A General Purpose Monte Carlo N-Particle Transport Code, Version 5. LA-UR-03-1987, Los Alamos National Laboratory, 2003. |
2 | ANSI/ANS-6, 4.3. Gamma Ray Attenuation Coefficient and Buildup Factors for Engineering Materials, American Nuclear Society, La Grange Park in Illinois, 1991. |
3 | F. Vermeersch, Dose Assessment and Dose Optimisation in Decommissioning Using the VISIPLAN 3D ALARA Planning Tool, Radiation protection and decommissioning ABR/BVS, Brussels, 2003, pp. 1-7. |
4 | J. Bratteli, HVRC VRdose Planner User Guide, Institute for Energy Technology Halden Virtual Reality Centre, 2015, pp. 1-64. |
5 | L.Q. Yang, Y.K. Liu, M.J. Peng, et al., A fast gamma-ray dose rate assessment method for complex geometries based on stylized model reconstruction, Nucl. Eng. Technol. 51 (2019) 1436-1443. DOI |
6 | Yang L.Q., Liu Y.K., Peng M.J., et al. A gamma-ray dose rate assessment method for arbitrary shape geometries based on voxelization algorithm, Radiat. Phys. Chem., 158 (2019) 122-130. DOI |
7 | O. Vela, E. De Burgos, J.M. Perez, Dose rate assessment in complex geometries, IEEE Trans. Nucl. Sci. 53 (2006) 304-311. DOI |
8 | B. Lindell, A history of radiation protection, Radiat. Prot. Dosim. 68 (1996) 83-95. DOI |
9 | J.F.E. Briesmeister, MCNP - A General Monte Carlo N-Particle Transport Code, 2010. |
10 | A. Ferrari, P.R. Sala, A. Fasso, J. Ranft, CERN 2005-10/SLAC-R-773 preprint, FLUKA: A Multi-Particle Transport Code, 2005. |
11 | I.M. Prokhorets, S.I. Prokhorets, M.A. Khazhmuradov, Point-kernel method for radiation fields simulation, Prob. Atomic Sci. Technol. 5 (2007) 106-109. |
12 | K.V. Subbaiah, R. Sarangapani, IGSHIELD: a new interactive point kernel gamma ray shielding code, Ann. Nucl. Energy 35 (2008) 2234-2242. DOI |
13 | ANS-6.1.1 Working Group, M.E. Battat, American National Standard Neutron and Gamma-Ray Flux-To-Dose Rate Factors, ANSI/ANS-6.1.1-1977 (N666), American Nuclear Society, LaGrange Park, Illinois, 1977. |
14 | ICRP Committee 3 Task Group, P. Grande, M.C. O'Riordan, Data for Protection against Ionizing Radiation from External Sources: Supplement to ICRP Publication 15, ICRP-21, International Commission on Radiological Protection, Pergamon Press, 1971. |
15 | Y. Harima, An approximation of gamma ray buildup factor by modified geometric progression, Nucl. Sci. Eng. 83 (1983) 299-309. DOI |
16 |
U.T. Lin, S.H. Jiang, A dedicated empirical formula for |
![]() |