1 |
IAEA, Reference Data Series, Nuclear Power Reactors in the World, No. 2, International Atomic Energy Agency, 2015.
|
2 |
Design and Engineering Survey Institute, Safety Analysis Report for the Bushehr Nuclear Power Plant, Atomenergoergoproekt, Moscow, 2003.
|
3 |
Y. Semchenkov, Y. Styrin, Advancing of VVER Reactor Core, 2010. Bulgaria, Varna.
|
4 |
V.I. Koulikov, T.F. Makarchuk, N.S. Tikhonov, Implementation of burnup credit in spent fuel management systems, Proceedings of an Advisory Group meeting held in Vienna, 20-24 October, IAEA, Vienna, 1997.
|
5 |
IAEA TECDOC, Operation and Maintenance of Spent Fuel Storage and Transportation Casks/Containers, No. 1532, Vienna, Austria, International Atomic Energy Agency (IAEA), 2007 [CD-ROM].
|
6 |
T. Funke, Ch. Henig, 1000/19: development and design of a new transport and storage cask, in: Proceedings of the International Youth Nuclear Congress, 20 - 26 September, Interlaken, Switzerland, 2008.
|
7 |
S.A. Mazur, Development of the Container Fleet for SNF Transportation, OJSC Federal Centre for Nuclear and Radiation Safety, Moscow, 2014.
|
8 |
T. Makarchuk, Experience of cask technology for SNF management, in: International Conference on the Management of Spent Fuel in Nuclear Power Reactors, IAEA, Vienna, 2015.
|
9 |
A.M. Kirkin, A.V. Kuryndin, A.A. Stroganov, Implementation of guidance for an integrated transport and storage safety case for dual purpose casks for spent nuclear fuel in Russian regulatory document, in: International Conference on Management of Spent Fuel from Nuclear Power Reactors: An Integrated Approach to the Back End of the Fuel Cycle, IAEA, Vienna, 2015.
|
10 |
IAEA TECDOC, Guidance for Preparation of a Safety Case for a Dual Purpose Cask Containing Spent Fuel, International Atomic Energy Agency (IAEA), Vienna, 2013.
|
11 |
J.H. Ko, et al., Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions, Nucl. Eng. Technol. 46 (2014) 547-556.
DOI
|
12 |
B. Droste, Overview of preparation of a safety case for a dual purpose cask for storage and transport of spent fuel and recommendations to WASSC and TRANSSC from WASSC/TRANSSC Working Group, in: International Workshop on the Development and Application of a Safety Case for Dual Purpose Casks for Nuclear Spent Fuel, IAEA, Vienna, 2014.
|
13 |
M. Asami, K. Sawada, A. Konnai, N. Odano, Application of dose evaluation of the MCNP code for the spent fuel transport cask, Prog. Nucl. Sci. Technol. 2 (2011) 855-859.
DOI
|
14 |
J.K. Shultis, Radiation Analysis of a Spent-fuel Storage Cask, Department of Mechanical and Nuclear Engineering, Kansas State University, Manhattan, USA, 2000.
|
15 |
C.J. Park, C.J. Jeong, D.K. Min, H.Y. Kang, W.S. Choi, J.C. Lee, G.S. Bang, K.S. Seo, Shielding performance of a newly designed transport cask in the advanced conditioning spent fuel pyroprocess facility, Nucl. Eng. Technol. 40 (2008) 319-326.
DOI
|
16 |
I.J. Cho, J.N. Jang, G.S. You, J.S. Yoon, Neutron and gamma shielding estimation for the KN-12 cask, J. Nucl. Sci. Technol. 45 (2008) 54-57.
DOI
|
17 |
M. Asami, H. Sawamura, K. Nishimura, Monte Carlo shielding calculations for a spent fuel transport cask with automated Monte Carlo variance reduction, J. Nucl. Sci. Technol. 2 (2011) 860-865.
DOI
|
18 |
M. Rezaeian, J. Kamali, Radioactive source specification of Bushehr's VVER-1000 spent fuels, Sci. Technol. Nucl. Ins. 2016 (2016) 4579738, http://dx.doi.org/10.1155/2016/4579738.
DOI
|
19 |
Los Alamos National Laboratory, User Manual Monte Carlo N-particle Transport Code System, Los Alamos National Laboratory, New Mexico, 2000.
|
20 |
IAEA Safety Standards, Regulations for the Safe Transport of Radioactive Material, Specific Safety Requirements No. SSR-6, International Atomic Energy Agency, 2012.
|
21 |
M.A. Kiani, S.J. Ahmadi, M. Outokesh, Fabrication of "Boron-Clay-Polymer" and "Lead-Clay-Polymer" Nanocomposites for Radiation Shielding of Neutron and Gamma Rays, M.S. thesis, Sharif University of Technology, Tehran, Iran, 2014.
|
22 |
M.B. Emmett, Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle, Oak Ridge National Laboratory: ORNL/TM-1999/207, USA, 2000.
|
23 |
I.I. Linge, E.F. Mitenkova, N.V. Novikov, End-to-end calculation of the radiation characteristics of VVER-1000 spent fuel assemblies, Phys. At. Nucl. 75 (2012) 1603-1615.
DOI
|
24 |
R.G. Williams, C.J. Gesh, R.T. Pagh, Compendium of Material Composition Data for Radiation Transport Modeling, Pacific Northwest National Laboratory: PNNL-15870 Rev. 1, USA, 2011.
|
25 |
P. Petrov, Calculation of the neutron sources in the spent nuclear fuel from WWER-1000, Compt. Rend. Acad. Bulg. Sci. 61 (2008) 885-890.
|
26 |
M. Rezaeian, J. Kamali, Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies, Kerntechnik 81 (2016) 640-646.
DOI
|
27 |
M. Rezaeian, J. Kamali, Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality, Appl. Radiat. Isot 119 (2017) 80-85.
DOI
|