Voir la notice de l'article provenant de la source Math-Net.Ru
@article{UZERU_2017_51_1_a10, author = {N. H. Baghdasaryan and S. A. Bznuni and A. M. Amirjanyan}, title = {Assessment of the reactivity bias and bias uncertainty due to {WWER-440} fuel depletion uncertainties}, journal = {Proceedings of the Yerevan State University. Physical and mathematical sciences}, pages = {60--65}, publisher = {mathdoc}, volume = {51}, number = {1}, year = {2017}, language = {en}, url = {http://geodesic.mathdoc.fr/item/UZERU_2017_51_1_a10/} }
TY - JOUR AU - N. H. Baghdasaryan AU - S. A. Bznuni AU - A. M. Amirjanyan TI - Assessment of the reactivity bias and bias uncertainty due to WWER-440 fuel depletion uncertainties JO - Proceedings of the Yerevan State University. Physical and mathematical sciences PY - 2017 SP - 60 EP - 65 VL - 51 IS - 1 PB - mathdoc UR - http://geodesic.mathdoc.fr/item/UZERU_2017_51_1_a10/ LA - en ID - UZERU_2017_51_1_a10 ER -
%0 Journal Article %A N. H. Baghdasaryan %A S. A. Bznuni %A A. M. Amirjanyan %T Assessment of the reactivity bias and bias uncertainty due to WWER-440 fuel depletion uncertainties %J Proceedings of the Yerevan State University. Physical and mathematical sciences %D 2017 %P 60-65 %V 51 %N 1 %I mathdoc %U http://geodesic.mathdoc.fr/item/UZERU_2017_51_1_a10/ %G en %F UZERU_2017_51_1_a10
N. H. Baghdasaryan; S. A. Bznuni; A. M. Amirjanyan. Assessment of the reactivity bias and bias uncertainty due to WWER-440 fuel depletion uncertainties. Proceedings of the Yerevan State University. Physical and mathematical sciences, Tome 51 (2017) no. 1, pp. 60-65. http://geodesic.mathdoc.fr/item/UZERU_2017_51_1_a10/
[1] G. Radulescu, I.C. Gauld, G. Ilas, J.C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses. Isotopic Composition Predictions, NUREG/CR-7108, 2012
[2] I.C. Gauld, Strategies for Application of Isotopic Uncertainties in Burnup Credit, NUREG/CR-6811, 2003
[3] L.J. Jardine, Radiochemical Assays of Irradiated VVER-440 Fuel for Use in Spent Fuel Burnup Credit Activities, UCRL-TR-212202, 2005
[4] R.E. Odeh, D.B. Owen, Tables for Normal Tolerance Limits, Sampling Plans and Screening, Marcel Dekker Inc., NY and Basel, 1980 | MR | Zbl
[5] J.T. Goorley, F.B. Brown, J.S. Hendricks et al., MCNP6TM User’s Manual, 2013
[6] M.B. Chadwick, M. Herman, P. Oblozinsk‘ y 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 | DOI
[7] J.L. Conlin et al., Listing of Available ACE Data Tables, LA-UR-13-21822, Los Alamos National Laboratory, 2014
[8] Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Cask Interim Staff Guidance-8, Revision 3, 2012
[9] J.C. Wagner, M.D. DeHart, C.V. Parks, Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses, NUREG/CR-6801, 2003
[10] F.B. Brown, A Review of Best Practices for Monte Carlo Criticality Calculations, LA-UR-09-3136, ANS NCSD, Richland, WA, 2009
[11] F.B. Brown, On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality Calculations, PHYSOR. LA-UR-06-3737, Vancouver, 2006