Geodesic
Development of optimal fuel loading configurations for Armenian NPP spent nuclear fuel transport cask
Proceedings of the Yerevan State University. Physical and mathematical sciences, no. 2 (2016), pp. 53-56.

Voir la notice de l'article provenant de la source Math-Net.Ru

Since transition of the fuel used in NPP from initial enrichment of $3.6\%$ to $3.82\%$ a necessity arises of revaluation of the security of transportation containers of spent nuclear fuel and based on it appropriate design modifications. To ensure subcriticality of containers borated steel insets are used. In this paper the results of study of optimal spatial configuration of borated and regular stainless steel guide sleeves configurations that allow meeting regulatory requirements on criticality safety. The model of the SNF transport cask was developed by KENO-VI code of SCALE 6.1 package. Isotopic composition of WWER-440 SNF was calculated by ORIGEN-S code of SCALE 6.1 package.
Keywords: spent nuclear fuel, criticality safety, spent fuel transport and storage, burnup credit. 
@article{UZERU_2016_2_a8,
     author = {N. H. Baghdasaryan},
     title = {Development of optimal fuel loading configurations for {Armenian} {NPP} spent nuclear fuel transport cask},
     journal = {Proceedings of the Yerevan State University. Physical and mathematical sciences},
     pages = {53--56},
     publisher = {mathdoc},
     number = {2},
     year = {2016},
     language = {en},
     url = {http://geodesic.mathdoc.fr/item/UZERU_2016_2_a8/}
}
TY  - JOUR
AU  - N. H. Baghdasaryan
TI  - Development of optimal fuel loading configurations for Armenian NPP spent nuclear fuel transport cask
JO  - Proceedings of the Yerevan State University. Physical and mathematical sciences
PY  - 2016
SP  - 53
EP  - 56
IS  - 2
PB  - mathdoc
UR  - http://geodesic.mathdoc.fr/item/UZERU_2016_2_a8/
LA  - en
ID  - UZERU_2016_2_a8
ER  - 
%0 Journal Article
%A N. H. Baghdasaryan
%T Development of optimal fuel loading configurations for Armenian NPP spent nuclear fuel transport cask
%J Proceedings of the Yerevan State University. Physical and mathematical sciences
%D 2016
%P 53-56
%N 2
%I mathdoc
%U http://geodesic.mathdoc.fr/item/UZERU_2016_2_a8/
%G en
%F UZERU_2016_2_a8
N. H. Baghdasaryan. Development of optimal fuel loading configurations for Armenian NPP spent nuclear fuel transport cask. Proceedings of the Yerevan State University. Physical and mathematical sciences, no. 2 (2016), pp. 53-56. http://geodesic.mathdoc.fr/item/UZERU_2016_2_a8/

[1] Safety Analysis Report for Medzamor NUHOMS Storage, DOS-06-00029988, Revision 0, June 2006, 2006

[2] Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material, IAEA Safety Guide, TS-G-1.1 (ST-2)

[3] ANPP Technical Specifications

[4] D.F. Hollenbach, L.M. Petrie, S. Goluoglu, N.F. Landers, M.E. Dunn, KENO-VI: A General Quadratic Version of the Keno Program, ORNL/TM-2005/39 Version 6, II, Sect. F17, 2005

[5] W.J. Marshall, B.T. Rearden, Criticality Safety Validation of Scale 6.1, ORNL/TM-2011/450

[6] M.B. Chadwick, M. Herman et al., “ENDF/B-VII.1 Nuclear Data for Science and Technology, Cross Sections, Covariances, Fission Product Yields and Decay Data”, Nuclear Data Sheets, 112 (2011), 2887–2996

[7] M.L. Williams, M. Asgari, D.F. Hollenbach, CENTRM: A One-Dimensional Neutron Transport Code for Computing Pointwise Energy Spectra, ORNL/TM-2005/39 Version 6 , II, Sect. F18

[8] ORIGEN-ARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay and Source Term Analysis, ORNL/TM-2005/39 Version 6, I, Sect. D1., 2005

[9] Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks, US NRC Spent Fuel Project Office Interim Staff Guidance 8, Rev-03

[10] B.L. Broadhead et al., Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel, ORNL/TM-12742, Oak Ridge National Laboratory, 1995