Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments-Reference-Cited by-同舟云学术

Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments

Published:1997-02 Issue:2 Volume:117 Page:206-222
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Broadhead Bryan L.¹,Tang Jabo S.¹,Childs Robert L.¹,Parks Cecil V.¹,Taniuchi Hiroaki¹

Affiliation:

1. Oak Ridge National Laboratory, Computational Physics and Engineering Division P.O. Box 2008, Oak Ridge, Tennessee 37831-6370

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/NT97-A35326

Reference18 articles.

1. M. A. McKinnon, J. M. CREER, C. L. WHEELER, J. E. TANNER, E. R. GILBERT, R. L. GOODMAN, D. P. BATALO, D. A. DZIADOSZ, E. V. MOORE, D. H. SCHOONEN, M. F. JENSEN, and J. H. BROWDER, “The MC-10 PWR Spent-Fuel Storage Cask: Testing and Analysis,” PNL-6139/NP-5268, Pacific Northwest Laboratory (1987).

2. J. M. CREER, R. A. McCann, M. A. McKinnon, J. E. TANNER, E. R. GILBERT, R. L. GOODMAN, D. H. SCHOONEN, M. JENSEN, C. MULLEN, B. A. DZIADOSZ, and E. V. MOORE, “CASTOR-V/21 PWR Spent Fuel Storage Cask Performance Testing and Analyses,” PNL-5917/NP-4887, Pacific Northwest Laboratory (1986).

3. M. A. McKinnon, R. E. DODGE, R. C. SCHMITT, L. E. ESLINGER, and G. DINEEN, “Performance Testing and Analyses of the VSC-17 Ventilated Concrete Cask,” PNL-7839/TR-100305, Pacific Northwest Laboratory (1992).

4. M. A. McKinnonn, T. E. MICHENER, M. F. JENSEN, and G. R. RODMAN, “Testing and Analyses of the TN-24P PWR Spent-Fuel Dry Storage Cask Loaded with Consolidated Fuel,” PNL-6631/NP-6191, Pacific Northwest Laboratory (1989).

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Study of the Reduction of Neutron Flux Through the Iron Material Using GEANT4 Simulations;Journal of Computational and Theoretical Transport;2024-05-09

2. A Monte Carlo study on the gamma-ray buildup factors for the linear sources embedded in a cylindrical shield;Journal of Instrumentation;2020-11-13

3. GEANT4 and PHITS simulations of the shielding of neutrons from the 252Cf source;Journal of the Korean Physical Society;2014-09

4. Effects of Source and Geometry Modeling on the Shielding Calculations for a Spent Nuclear Fuel Dry Storage Cask;Nuclear Technology;2013-05

5. Safety analysis of irradiated RBMK-1500 nuclear fuel transportation in newly developed container;Nuclear Engineering and Design;2010-10