Surface Dose Rate Calculations of a Spent-Fuel Storage Cask by Using MAVRIC and Its Comparison with SAS4 and MCNP-Reference-Cited by-同舟云学术

Surface Dose Rate Calculations of a Spent-Fuel Storage Cask by Using MAVRIC and Its Comparison with SAS4 and MCNP

Published:2011-07 Issue:1 Volume:175 Page:343-350
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chen Y. F.¹,Sheu R. J.²,Jiang S. H.¹³,Wang J. N.⁴,Lin U. T.⁴

Affiliation:

1. National Tsing Hua University, Department of Engineering and System Science Hsinchu, Taiwan

2. National Synchrotron Radiation Research Center, Hsinchu Science Park Hsinchu, Taiwan

3. National Tsing Hua University, Institute of Nuclear Engineering and Science Hsinchu, Taiwan

4. Institute of Nuclear Energy Research, Taoyuan 325, Taiwan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT11-A12306

Reference11 articles.

1. Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function

2. Monte Carlo variance reduction with deterministic importance functions

3. D. E. PEPLOW, “MAVRIC: MONACO with Automated Variance Reduction Using Importance Calculations,” ORNL/TM-2005/39, Version 6, Vol. I, Sec. S6, Oak Ridge National Laboratory (2009).

4. “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations,” ORNL/TM-2005/39, Version 6, Vols. I, II, and III, Oak Ridge National Laboratory (2009).

5. J. S. TANG and M. B. EMMETT, “SAS4: A Monte Carlo Cask Shielding Analysis Module Using an Automated Biasing Procedure,” ORNL/TM-2005/39, Version 5.1, Vol. I, Sec. S4, Oak Ridge National Laboratory (2006).

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