과제정보
This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No. NRF-2019M2D2A1A03058371).
참고문헌
- J. Jang, B. Ebiwonjumi, W. Kim, J. Park, J. Choe, D. Lee, Validation of spent nuclear fuel decay heat calculation by a two-step method, Nucl. Eng. Technol. 53 (2021) 44-60, https://doi.org/10.1016/j.net.2020.06.028.
- J. Jang, B. Ebiwonjumi, W. Kim, A. Cherezov, J. Park, D. Lee, Verification and validation of isotope inventory prediction for back-end cycle management using two-step method, Nucl. Eng. Technol. 53 (2021) 2104-2125, https://doi.org/10.1016/j.net.2021.01.009.
- J. Park, J. Jang, H. Kim, J. Choe, D. Yun, P. Zhang, A. Cherezov, D. Lee, RAST-K v2-three-dimensional nodal diffusion code for pressurized water reactor core analysis, Energies 13 (2020) 6324, https://doi.org/10.3390/en13236324.
- Current Status of World Nuclear Fuel Cycle Technology (III): Russia and Soviet Union, KAERI/AR-826/2008, KAERI, 2008. https://inis.iaea.org/collection/NCLCollectionStore/_Public/41/067/41067574.pdf.
- The VVER today, ROSATOM. https://rosatom.ru/upload/iblock/0be/0be1220af25741375138ecd1afb18743.pdf. Accessed May 31.
- L.J. Jardine, Radiochemical Assays of Irradiated VVER-440 Fuel for Use in Spent Fuel Burnup Credit Activities, UCRL-TR-212202, Lawrence Livermore National Laboratory, 2005.
- Y. Bilodid, E. Fridman, T. Lotsch, X2 VVER-1000 benchmark revision: fresh HZP core state and the reference Monte Carlo solution, Ann. Nucl. Energy 144 (2020), https://doi.org/10.1016/j.anucene.2020.107558.
- J. Jang, S. Dzianisau, D. Lee, Development of nodal diffusion code RAST-V for Vodo-Vodyanoi Energetichesky reactor analysis, Nucl. Eng. Technol. 54 (2022) 3494-3515, https://doi.org/10.1016/j.net.2022.04.007.
- Online, Power reactor information system. https://pris.iaea.org/PRIS/CountryStatistics/ReactorDetails.aspx?current=448, International Arts and Entertainment Alliance.
- Online, Novovoronezh Unit 4 Completes Upgrade, World nuclear news, 2018. https://world-nuclear-news.org/Articles/Novovoronezh-unit-4-completes-upgrade.
- L. Markova, Continuation of the VVER Burnup Credit Benchmark: Evaluation of CB1 Results, Overview of CB2 Results to Date and Specification of CB3, 8th Symposium AER, Bystrice n. Pernstejnem, 1998. https://inis.iaea.org/collection/NCLCollectionStore/_Public/32/068/32068921.pdf.
- L. Markova, Specification for CB 6 Benchmark on VVER-440 Final Disposal, 2010. https://www.oecd-nea.org/science/wpncs/buc/specifications/CB6-VVER-Disposal-benchmark.pdf.
- B. Ebiwonjumi, S. Choi, M. Lemaire, D. Lee, H.C. Shin, Validation of lattice physics code Stream for predicting pressurized water reactor spent nuclear fuel isotopic inventory, Ann. Nucl. Energy 120 (2018) 431-449, https://doi.org/10.1016/j.anucene.2018.06.002.
- G.I. Radulescu, C.G. Gauld, J. Llas, C. Wagner, NUREG/CR-7108 an Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions, Oak Ridge National Laboratory, April 2012.
- M. J, D. Scaglione, E.J. Mueller, C.W. Wagner, J. Marshall, NUREG/CR-7109, an Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (Keff) Predictions, Oak Ridge National Laboratory, April 2012.
- User's Guide HDF5 Release 1.10, The HDF Group, 2019. https://portal.hdfgroup.org/display/HDF5/HDF5+User+Guides?preview=/53610087/53610088/Users_Guide.pdf.
- B. Vrban, J. Luley, S. Cerba, F. Osusky, V. Necas, The VVER-440 Burnup Credit Computational Benchmark Used for the SCALE System Qualification, Applied Physics of Condensed Matter, APCOM 2018, 2018.
- A. Ranta-aho, Validation of Depletion Codes against VVER-440 Spent Fuel Data, vol. 31, NEA/NSC/DOC(2006, Prague, Czech Republic, 2006. https://www.oecd.org/officialdocuments/publicdisplaydocumentpdf/?cote=NEA/NSC/DOC(2006)31&docLanguage=En.
- J. Jang, Y. Chezerov, T. Jo, S. Quoc, W. Dzianisau, J. Lee, D. Park, Lee, Verification of RAST-K Hexagonal Transient Solver with OCED/NEA Benchmark Problem of KALININ-3 NPP, KNS Winter Meeting, Korea, 2020. Online.
- S. Quoc, W. Dzianisau, D. Lee, J. Lee, T. Jang T, Verification of RAST-K Hexagonal Analysis Module with SNR and VVER-440 Benchmarks, KNS Winter Meeting, Korea, 2020 [Online].
- J. Jang, M. Hursin, W. Lee, A. Pautz, M. Papadionysiou, H. Ferroukhi, D. Lee, Analysis of Rostov-II benchmark using conventional two-step code systems, Energies 15 (2022) 3318, https://doi.org/10.3390/en15093318.
- J. Jang, Development of Nodal Diffusion Code for VVER and HTGR Analysis with Advanced Semi Analytic Nodal Method, Doctoral Thesis, Ulsan National Institute of Science and Technology, 2023.
- J.Y. Cho, C.H. Kim, Higher order polynomial expansion nodal method for hexagonal core neutronics analysis, Ann. Nucl. Energy 25 (1998) 1021-1031, https://doi.org/10.1016/S0306-4549(97)00101-1.
- S. Choi, W. Kim, J. Choe, W. Lee, H. Kim, B. Ebiwonjumi, E. Jeong, K. Kim, D. Yun, H. Lee, D. Lee, Development of high-fidelity neutron transport code STREAM, Comput. Phys. Commun. 264 (2021) 107915, https://doi.org/10.1016/j.cpc.2021.107915.
- A. Quarteroni, R. Sacco, F. Saleri. Numerical Mathematics, 2nd ed., Springer, 2007, ISBN 978-1-4757-7394-1 https://doi.org/10.1007/b98885.
- R.J.J. Stamm'ler, M.J. Abbate, Methods of Steady-State Reactor Physics in Nuclear Design, Academic Press Inc. (LONDON) LTD, 1983, 0-12-663320-7.
- S. Borresen, T. Bahadir, M. Kruners, Validation of CMS/SNF Calculations against Preliminary CLAB Decay Heat Measurements, Transactions of the American nuclear society, Omni Shoreham Hotel Washington, D.C., 2004. November 14-18.
- S. Borresen, Spent fuel analyses based on in-core fuel management calculations, in: Proc. PHYSOR (2004). The Physics of Fuel Cycles and Advanced Nuclear Systems, Global Developments, Chicago, Illinois, 2004. April 25-29.
- bib29sref29 Markova, L., Simplified benchmark specif. Based on vol. 2670 ISTC VVER PIE. 12th Meeting of AER Working Group E on "Physical Problems of Spent Fuel, Radwaste and Nuclear Power Plants Decommissioning", Modra, Slovakia, April 16-18, 2007, https://www.oecd-nea.org/science/wpncs/buc/specifications/istc2670/2670%20benchmark%20specification.pdf.
- F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havluj, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. Rantamaki, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S.V. Winckel, A. Vasiliev, T. Watanabe, T. Yamamoto, T. Yamamoto, SFCOMPO-2.0: an OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data, Ann. Nucl. Energy 110 (2017) 779-788, https://doi.org/10.1016/j.anucene.2017.07.022.s.
- M.B. Chadwick, P. Oblozinsky, M. Herman, N.M. Greene, R.D. McKnight, D. L. Smith, P.G. Young, R.E. MacFarlane, G.M. Hale, S.C. Frankle, A.C. Kahler, T. Kawano, R.C. Little, D.G. Madland, P. Moller, R.D. Mosteller, P.R. Page, P. Talou, H. Trellue, M.C. White, W.B. Wilson, R. Arcilla, C.L. Dunford, S.F. Mughabghab, B. Pritychenko, D. Rochman, A.A. Sonzogni, C.R. Lubitz, T.H. Trumbull, J. P. Weinman, D.A. Brown, D.E. Cullen, D.P. Heinrichs, D.P. McNabb, H. Derrien, M. E. Dunn, N.M. Larson, L.C. Leal, A.D. Carlson, R.C. Block, J.B. Briggs, E.T. Cheng, H.C. Huria, M.L. Zerkle, K.S. Kozier, A. Courcelle, V. Pronyaev, S.C. van der Marck, ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets, ENDF/B. 107 (2006) 2931-3060, https://doi.org/10.1016/j.nds.2006.11.001.
- O. Leray, D. Rochman, P. Grimm, H. Ferroukhi, A. Vasiliev, M. Hursin, G. Perret, A. Pautz, Nuclear data uncertainty propagation on spent fuel nuclide compositions, Ann. Nucl. Energy 94 (2016) 603-611, https://doi.org/10.1016/j.anucene.2016.03.023.
- J. Jang, C. Kong, B. Ebiwonjumi, Y. Jo, D. Lee, Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with Stream/RAST-K, Ann. Nucl. Energy 158 (2021), https://doi.org/10.1016/j.anucene.2021.108267.
- Techniques and equipment to determine nuclide composition, Isotopic Mass and Fuel Burnup Fraction in Fuel Samples. Interim Progress Report, Task 6, Burnup Credit Project, 2003, p. 2670р.
- ASTM E-244-80, Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Mass Spectrometric Method).
- MATLAB, The MathWorks Incorp, Natick, Massachusetts, 2022.
- J. Jang, C. Kong, B. Ebiwonjumi, A. Cherezov, Y. Jo, D. Lee, Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K, Nucl. Eng. Technol. 53 (2021) 2803-2815, https://doi.org/10.1016/j.net.2021.03.010.
- B. Ebiwonjumi, S. Choi, M. Lemaire, D. Lee, H.C. Shin, H.S. Lee, Verification and validation of radiation source term capabilities in Stream, Ann. Nucl. Energy 124 (2019) 80-87, https://doi.org/10.1016/j.anucene.2018.09.034.
- T.S. Lotsch, E. Kliem, V. Bilodid, A. Khalimonchuk, Y. Kuchin, M. Ovdienko, R. Ieremenko, G. Blank, Schultz, The x2 benchmark for vver-1000 reactor calculations results and status, in: Novel Vision of Scientific & Technical Support for Regulation of Nuclear Energy Safety: Competence, Transparency, Responsibility, Dedicated to the 25th Anniversary of the SSTC, National Rosacea Society, Kiev, Ukraine, 2017. March 22-23.
- 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, https://doi.org/10.1016/j.apradiso.2016.10.008.
- J. Leppanen, M. Pusa, T. Viitanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: status development and applications in 2013, Ann. Nucl. Energy 82 (2015) 142-150, https://doi.org/10.1016/j.anucene.2014.08.024.
- S. Choi, W. Kim, J. Choe, W. Lee, H. Kim, B. Ebiwonjumi, E. Jeong, H. Lee, D. Yun, D. Lee, Development of high-fidelity neutron transport code STREAM, Comput. Phys. Commun. 264 (2021), 107915, https://doi.org/10.1016/j.cpc.2021.107915.
- S. Choi, K. Smith, H. Chul Lee, D. Lee, Impact of inflow transport approximation on light water reactor analysis, J. Comput. Phys. 299 (2015) 352-373, https://doi.org/10.1016/j.jcp.2015.07.005.
- H. Yun, K. Park, W. Choi, S.G. Hong, An efficient evaluation of depletion uncertainty for a GBC-32 dry storage cask with PLUS7 fuel assemblies using the Monte Carlo sampling method, Ann. Nucl. Energy 110 (2017) 679-691.
- S. Choi, H. Lee, S.G. Hong, D. Lee, Resonance self-shielding methodology of new neutron transport code STREAM, J. Nucl. Sci. Technol. 52 (9) (2015) 1133-1150, https://doi.org/10.1080/00223131.2014.993738.
- T. Lahtinen, Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code, Kerntechnik 79 (2014) 303-313, https://doi.org/10.3139/124.110464.
- Thermal Neutron Capture Cross Sections Resonance Integrals and G-Factors, S.F. Mughabghab, Brookhaven National Laboratory, Upton, New York, U.S.A, 2003, pp. 11973-15000. https://www.osti.gov/etdeweb/servlets/purl/20332542.February.
- I.C. Gauld, U. Mertyurek, C. I, U. Gauld, Mertyurek, alidation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit, Nucl. Eng. Des. 345 (2019) 110-124, https://doi.org/10.1016/j.nucengdes.2019.01.026.
- R. Ihaka, R. Gentleman, R: a language for data analysis and graphics, J. Comput. Graph Stat. 5 (1995) 299-314, https://doi.org/10.2307/1390807.
- W.R. Blischke, D.N. Prabhakar Murthy, Reliability: Modeling, Prediction, and Optimization, Wiley, 2000, 9780471184508.