과제정보
This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No. NRF-2019M2D2A1A03058371).
참고문헌
- K. Ilieva, S. Belousov, A. Ballesteros, et al., Reactor dosimetry for VVERs RPV lifetime assessment, Prog. Nucl. Energy 51 (2009) 1-13. https://doi.org/10.1016/j.pnucene.2007.12.004
- M. Kostal, M. Schulc, V. Rypar, et al., VVER-1000 Mock-Up Physics Experiments Hexagonal Lattices (1.275 Cm Pitch) of Low Enriched U(2.0, 3.0, 3.3 wt.% 235U)O2 Fuel Assemblies in Light Water with H3BO3, OECD/NEA IRPhE Project, LR(0)-VVER-RESR-002, 2006.
- M. Kostal, V. Rypar, V. Juricek, The criticality of VVER-1000 mock-up with different H3BO3 concentration, Ann. Nucl. Energy 60 (1) (2013) 1-7. https://doi.org/10.1016/j.anucene.2013.04.014
- B. Osmera, J. Mikus, F. Hudec, et al., Radiation Field Parameters for Pressure Vessel Monitoring in VVER-1000 Using the NRI LR-0 Experimental Reactor (~1990), OECD/NEA SINBAD REACTOR, 2009. Package NEA-1517/82.
- M. Kostal, V. Rypar,M. Svadlenkova, The pin power distribution in theVVER-1000 mock-up on the LR-0 research reactor, Nucl. Eng. Des. 242 (1) (2012) 201-214. https://doi.org/10.1016/j.nucengdes.2011.09.010
- M. Kostal, M. Svadlenkova, J. Milcak, Absolute determination of power density in the VVER-1000 mock-up on the LR-0 research reactor, Appl. Radiat. Isot. 78 (1) (2013) 38-45. https://doi.org/10.1016/j.apradiso.2013.03.094
- M. Kostal, M. Svadlenkova, J. Milcak, et al., Determination of critical assembly absolute power using post-irradiation activation measurement of week-lived fission products, Appl. Radiat. Isot. 89 (1) (2014) 18-24. https://doi.org/10.1016/j.apradiso.2014.01.004
- B. Ebiwonjumi, S. Choi, M. Lemaire, et al., 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
- J. Choe, S. Choi, P. Zhang, et al., Verification and validation of STREAM/RAST-K for PWR analysis, Nucl. Eng. Technol. 51 (2) (2019) 356-368. https://doi.org/10.1016/j.net.2018.10.004
- H. Lee, W. Kim, P. Zhang, et al., "Mcs - a Monte Carlo particle transport code for large-scale power reactor analysis," Ann. Nucl. Energy, vol. 139, 2020.
- V. Dos, H. Lee, Y. Jo, et al., Overcoming the challenges of monte-carlo depletion: application to a material-testing reactor with MCS code, Nucl. Eng. Technol. 52 (9) (2020) 1881-1895. https://doi.org/10.1016/j.net.2020.02.003
- J. Jang, W. Kim, S. Jeong, et al., Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask, Ann. Nucl. Energy 114 (2018) 495-509. https://doi.org/10.1016/j.anucene.2017.12.054
- J. Yu, H. Lee, M. Lemaire, H. Kim, et al., MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON, Comput. Phys. Commun. 238 (2019) 1-18. https://doi.org/10.1016/j.cpc.2019.01.001
- T.Q. Tran, J. Choe, X. Du, et al., Preliminary CEFR analysis by Monte Carlo codes, in: M&C 2019, Oregon, USA, 2019.
- M. Chadwick, M. Herman, P. Oblozinsky, et al., ENDF/B-VII.1 nuclear data for science and Technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112 (2011), 2887-2996. https://doi.org/10.1016/j.nds.2011.11.002
- D.A. Brown, M.B. Chadwick, R. Capote, et al., ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, Nucl. Data Sheets 148 (2018) 1-142. https://doi.org/10.1016/j.nds.2018.02.001
- X.B. Tran, N.Z. Cho, A study of neutronics effects of the spacer grids in a typical PWR via Monte Carlo calculation, Nucl. Eng. Technol. 48 (1) (2016) 33-42. https://doi.org/10.1016/j.net.2015.10.001
- M. Nowak, J. Miao, E. Dumonteil, et al., Monte Carlo power iteration: entropy and spatial correlations, Ann. Nucl. Energy 94 (2016) 856-868. https://doi.org/10.1016/j.anucene.2016.05.002