Sensitivity and uncertainty analysis for the UAM-SFR sub-exercises with linear regression from random sampling
Tài liệu tham khảo
Aures, A., Berner, N., Zwermann, W., 2020a. Closing the Gap Between Sensitivity Analyses Based on Perturbation Theory and Random Sampling, submitted to Proc. Best Estimate Plus Uncertainty Intl. Conf. (BEPU 2020), Giardini Naxos, Sicily, Italy.
Aures, A., Berner, N., Pautz, A., Zwermann, W., 2020b. Uncertainty and Sensitivity Analysis of PWR Mini-Core Transients in the Presence of Nuclear Data Uncertainty Using Non-Parametric Tolerance Limits, https://doi.org/10.1016/j.anucene.2019.107146, Annals of Nuclear Energy 137, ID 107146.
Bostelmann, F., Weiß, F.-P., Aures, A., Velkov, K., Zwermann, W., Rearden, B.T., Jessee, M.A., Williams, M.L., Wiarda, D., Wieselquist, W.A., 2015. Uncertainty and Sensitivity Analysis in Criticality Calculations with Perturbation Theory and Sampling, Proc. Joint Intl. Conf. on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (ANS MC2015), Nashville, TN, USA.
Bostelmann, F., Brown, N.R., Pautz, A., Rearden, B.T., Velkov, K., Zwermann, W., 2017. SCALE Multi-Group Libraries for Sodium-Cooled Fast Reactor Systems, Proc. Intl. Conf. on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017), Jeju, Korea.
Bostelmann, F., Zwermann, W., Pautz, A., 2018. SCALE Covariance Libraries for Sodium-Cooled Fast Reactor Systems, Proc. Intl. Conf. Reactor Physics Paving the Way Towards More Efficient Systems (PHYSOR 2018), Cancun, Mexico.
Buiron, L., Rimpault, G., Sciora, P., Stauff, N., Kim, T.K., Taiwo, T., Bostelmann, F., Pautz, A., Ivanov, K., Trivedi, I., Keresztúri, A., Aures, A., Velkov, K., Zwermann, W., Mikityuk, K., 2019. Benchmarks for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs, Version 1.6 (Draft), available from OECD/NEA.
Chadwick, 2011, ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nuclear Data Sheets, 112, 2887, 10.1016/j.nds.2011.11.002
Efron, 1981, The jackknife estimate of variance, Ann Statistics, 9, 10.1214/aos/1176345462
Horwedel, 1991, GRESS, a preprocessor for sensitivity studies of Fortran programs
Hou, J., Maras, C., Gozum, C., Avramova, M., Ivanov, K., 2019. Comparative Analysis of Solutions of Neutronics Exercises of the LWR UAM Benchmark, Proc. Intl. Conf. on Mathematics and Computational Methods (M&C 2019), Portland, OR, USA.
Kodeli, 2011, The SUSD3D code for cross-section sensitivity and uncertainty analysis – recent development, Trans. Am. Nucl. Soc., 104, 791
Lee, H., Kong, C., Lee, D., 2014. Status of Monte Carlo Code Development at UNIST. Proc. Intl. Conf. The Role of Reactor Physics Toward a Sustainable Future (PHYSOR 2014), Kyoto, Japan.
Leppänen, 2015, The Serpent Monte Carlo Code: status, development and applications in 2013, Ann. Nucl. Energy, 82, 142, 10.1016/j.anucene.2014.08.024
Mikityuk, 2017, ESFR-SMART: New Horizon-2020 Project on SFR Safety
OECD/NEA, 2014. Technology Roadmap Update for Generation IV Nuclear Energy Systems, Issued by the OECD Nuclear Energy Agency for the Generation IV International Forum.
Pelowitz, D.B., Ed., 2013. MCNP6 User’s Manual Version 1.0, Los Alamos National Laboratory Report LA-CP-13-00634.
Rearden, B.T. M.A. Jessee, M.A., Eds., 2018. SCALE Code System, ORNL/TM-2005/39, Version 6.2.3, Oak Ridge National Laboratory, Oak Ridge, TN, USA. Available from Radiation Safety Information Computational Center as CCC-834.
Ruggieri, J.M., Tommasi, J., Lebrat, J.F., Suteau, C., Plisson-Rieunier, D., De Saint Jean, C., Rimpault, G., Sublet, J.C., 2006. ERANOS 2.1: International Code System for GEN IV Fast Reactor Analysis, Proc. Intl. Conf. on Advances in Nuclear Power Plants (ICAPP'06), Reno, NV, USA.
Smith, M.A., Adams, C., Yang, W.S., Lewis, E.E., 2013. VARI3D & PERSENT: Perturbation and Sensitivity Analysis, Argonne National Laboratory Report ANL/NE-13/8, Lemont, IL, USA.
Williams, 2013, A statistical sampling method for uncertainty analysis with SCALE and XSUSA, Nucl. Technol., 183, 515, 10.13182/NT12-112
Zheng, 2018, SARAX: a new code for fast reactor analysis Part I: methods, Nucl. Eng. Design, 340, 421, 10.1016/j.nucengdes.2018.10.008
Zwermann, W., Gallner, L. Klein, M., Krzykacz-Hausmann, B., Pasichnyk, I., Pautz, A., Velkov, K., 2013. Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis, EPJ Web of Conferences 42, ID 03003.