Browse > Article
http://dx.doi.org/10.1016/j.net.2016.01.009

On-the-fly Estimation Strategy for Uncertainty Propagation in Two-Step Monte Carlo Calculation for Residual Radiation Analysis  

Han, Gi Young (Korea Institute of Nuclear Safety)
Kim, Do Hyun (Department of Nuclear Engineering, Hanyang University)
Shin, Chang Ho (Department of Nuclear Engineering, Hanyang University)
Kim, Song Hyun (Department of Nuclear Engineering, Hanyang University)
Seo, Bo Kyun (Korea Institute of Nuclear Safety)
Sun, Gwang Min (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.48, no.3, 2016 , pp. 765-772 More about this Journal
Abstract
In analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simulation. The first step (MC1) simulates neutron transport, and the second step (MC2) transports the decay photons emitted from the activated materials. In this process, the stochastic uncertainty estimated by the MC2 appears only as a final result, but it is underestimated because the stochastic error generated in MC1 cannot be directly included in MC2. Hence, estimating the true stochastic uncertainty requires quantifying the propagation degree of the stochastic error in MC1. The brute force technique is a straightforward method to estimate the true uncertainty. However, it is a costly method to obtain reliable results. Another method, called the adjoint-based method, can reduce the computational time needed to evaluate the true uncertainty; however, there are limitations. To address those limitations, we propose a new strategy to estimate uncertainty propagation without any additional calculations in two-step MC simulations. To verify the proposed method, we applied it to activation benchmark problems and compared the results with those of previous methods. The results show that the proposed method increases the applicability and user-friendliness preserving accuracy in quantifying uncertainty propagation. We expect that the proposed strategy will contribute to efficient and accurate two-step MC calculations.
Keywords
Error Propagation; On-the-fly; Monte Carlo; Residual Radiation; Stochastic Uncertainty;
Citations & Related Records
연도 인용수 순위
  • Reference
1 D.B. Pelowitz, MCNPX manual, version 2.7.0., La-Cp-11-00438, 2011.
2 Y. Chen, U. Fischer, Rigorous MCNP based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER, Fusion Eng. Des. 63 (2002) 107-114.
3 D.G. Cacuci, M. Ionescu-Bujor, I.M. Navon, Sensitivity and uncertainty analysis, volume II: Applications to large-scale systems, CRC Press, Florida, 2005.
4 D.E. Peplow, A.M. Ibrahim, R.E. Grove, Propagation of uncertainty from a source computed with Monte Carlo, Trans. Am. Nucl. Soc. 108 (2013) 643.
5 T.E. Booth, J.S. Hendricks, Importance estimation in forward Monte Carlo calculations, Fusion Sci. Technol. 5.1 (1984) 90-100.   DOI
6 K. Shibata, T. Nakagawa, T. Fukahori, O. Iwamoto, A. Ichihara, N. Iwamoto, K. Kosako, Recent advances in the JENDL project, International Conference on Nuclear Data for Science and Technology, EDP Sciences, 2007, pp. 727-732.
7 J.C. Wagner, E.L. Redmond, S.P. Palmtag, J.S. Hendricks, MCNP: Multigroup/adjoint capabilities, LA-12704, Los Alamos National Laboratory, NM, 1994.
8 N. Petoussi-Henss, W.E. Bolch, K.F. Eckerman, A. Endo, N. Hertel, J. Hunt, M. Zankl, Conversion coefficients for radiological protection quantities for external radiation exposures, Ann. ICRP 40.2 (2010) 1-257.   DOI
9 K. Tshoo, Y.K. Kim, Y.K. Kwon, H.J. Woo, G.D. Kim, Y.J. Kim, B.H. Kang, S.J. Park, Y.-H. Park, J.W. Yoon, J.C. Kim, J.H. Lee, C.S. Seo, W. Hwang, C.C. Yun, D. Jeon, J.C. Kim, Experimental systems overview of the Rare Isotope Science Project in Korea, Nucl. Instrum. Methods Phys. Res. Sect. B 317 (2013) 242-247.   DOI
10 L.R. Carroll, Predicting long-lived, neutron-induced activation of concrete in a cyclotron vault, 16th International Conference on the Application of Accelerators in Research and Industry, Denton (TX), November 1-5, 2000, pp. 301-304.
11 American Nation Standard, Nuclear analysis and design of concrete radiation shielding for nuclear power plants, ANSI/ANS-6.4-2006, American Nuclear Society, 2006.