Dose Evaluation for an Independent Spent-Fuel Storage Installation Using MAVRIC-Reference-Cited by-同舟云学术

Dose Evaluation for an Independent Spent-Fuel Storage Installation Using MAVRIC

Published:2011-07 Issue:1 Volume:175 Page:335-342
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sheu R. J.¹,Chen Y. F.²,Jiang S. H.²³,Wang J. N.⁴,Lin U. T.⁴

Affiliation:

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

2. National Tsing Hua University, Department of Engineering and System Science 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-A12305

Reference8 articles.

1. Study of the Site Dose Rate for the ISFSI Facility with Monte Carlo and Deterministic Methods

2. 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).

3. “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).

4. “MCNP—A General Monte Carlo N-Particle Transport Code,” Version 4C, LA-13709-M, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (2000).

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

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