The impact of fuel depletion scheme within SCALE code on the criticality of spent fuel pool with RBMK fuel assemblies |
Andrius Slavickas
(Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute)
Tadas Kaliatka (Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute) Raimondas Pabarcius (Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute) Sigitas Rimkevicius (Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute) |
1 | Advanced Light Water Reactor Utility Requirements Document, 1999. EPRI, TR-016780-V1R2. |
2 | Regulatory Guide 1.13 Spent Fuel Storage Facility Design Basis, US.NRC, 2007. |
3 | V. Vlaskin, G. Krivosein, B. Dizik, V. Stebenev, A. Kaliatka, E. Urbonaviꠑcius, Development of a management plan for beyond design basis accidents for the RBMK-1500 reactors of the Ignalina Nuclear Power Plant, Energetika 53 (2007) 19 (In Russian). |
4 | VATESI, Scientific and technical support during the control in connection with the transition to the use of 2.8% enriched uranium-erbium fuel in the aspects of radiation and nuclear safety assessment of Ignalina NPP, Tech. rep., 2004. TASpd -1299-70796. |
5 | L. Agrenius, Criticality Safety Calculations of Disposal Canisters, SKBdoc 1193244, Version 4.0, Svensk Karnbranslehatering AB, 2010. |
6 | V. Remeikis, J. Grineviciute, G. Duꠑskesas, L. Juodis, R. Plukiene, A. Plukis, Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. I. Safety improvement studies during operation, Nucl. Eng. Des. 380 (2021). ID 110952. |
7 | A. Slavickas, R. Pabarꠑcius, A. Tonkunas, S. Rimkevi ꠑcius, Neutron transport simulations of RBMK fuel assembly using multigroup and continuous energy data libraries within the SCALE code, Sci. Technol. Nucl. Install. 2021 (2021). ID 6673489. |
8 | Germina Ilas, Ian C. Gauld, Georgeta Radulescu, Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE, Ann. Nucl. Energy 46 (2012) 43-55. DOI |
9 | Bamidele Ebiwonjumi, Hyunsuk Lee, Wonkyeong Kim, Deokjung Lee, Validation of nuclide depletion capabilities in Monte Carlo code MCS, Nucl. Eng. Technol. 52 (9) (2020) 1907-1916. DOI |
10 | W. Marshall, B.J. Ade, S.M. Bowman, I.C. Gauld, G. Ilas, U. Mertyurek, G. Radulescu, Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems, US.NRC, April 2015. ORNL/TM-2014/240. |
11 | I.C. Gauld, U. Mertyurek, Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit, Nucl. Eng. Des. 345 (2019) 100-124. |
12 | M.I. Radaideh, D. Price, D. O'Grady, T. Kozlowski, Advanced BWR criticality safety part I: model development, model benchmarking, and depletion with uncertainty analysis, Prog. Nucl. Energy 113 (2019) 230-243. DOI |
13 | J. Cardoni, N. Jeffrey, Jankovsky, Fukushima Daiichi Radionuclide Inventories, Sep 2016. SAND-2016-9065R, United States. |
14 | SCALE/TRITON Primer, A Primer for Light Water Reactor Lattice Physics Calculations, November 2012. ORNL/TM-2011/21. |
15 | H. Smith, Modeling depletion simulations for a high-burnup, highly heterogeneous BWR fuel assembly with SCALE, in: Proc. PHYSOR - Advances in Reactor Physics, American Nuclear Society, Knoxville TN, USA, 2012, 15-20 April,. |
16 | C. Mesado, D. Morera, R. Miro, T. Barrachina, G. Verdu, Alberto Concejal, Amparo Soler, Jose Melara, Comparison of depletion results for a Boiling Water Reactor fuel element with CASMO and SCALE 6.1 (TRITON/NEWT), in: INAC - International Nuclear Atlantic Conference, 2013. Recife, PE, Brazil, November 24-29. |
17 | (Chapter 5). Accident analysis, Safety Analysis Report for Decommissioning Project for Ignalina NPP Unit 2 Final Shut Down and Defuelling Phase, Lithuanian Energy Institute, 2010. S/14-1037.8.9/SAAe/R:3. |
18 | R. Plukiene, A. Plukis, D. Germanas, V. Remeikis, Numerical sensitivity study of irradiated nuclear fuel evolution in the RBMK reactor, Lith. J. Phys. 49 (4) (2009) 461-469. DOI |
19 | K. Almenas, A. Kaliatka, E. Uspuras, Ignalina RBMK-1500. A Source Book, Lithuanian Energy Institute, 1998. |
20 | Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, ORNL/TM-2005/39, Version 6.1, June 2011. Available from Radiation Safety Information Computational Center at Oak Ridge Natl. Lab., CCC-785. |
21 | Spent Nuclear Fuel Assay Data for Isotopic Validation vol. 5, June 2011. OECD&NEA, NEA/NSC/WPNCS/DOC(2011). |
22 | L.C. Leal, H. Derrien, M.E. Dunn, D.E. Mueller, Assessment of Fission Product Cross-Section Data for Burnup Credit Applications, 2007. ORNL/TM-2005/65, December. |