참고문헌
- GIF, Technology Roadmap Update for Generation IV Nuclear Energy Systems, 2014.
- J. Serp, M. Allibert, O. Benes, S. Delpech, O. Feynberg, V. Ghetta, D. Heuer, D. Holcomb, V. Ignatiev, J.L. Kloosterman, L. Luzzi, E. Merle-Lucotte, J. Uhlir, R. Yoshioka, D. Zhimin, The molten salt reactor (MSR) in generation IV: overview and Perspectives, Prog. Nucl. Energy (2014) 1-13.
- IAEA, IAEA Safety Standard for Protecting People and Environment, Fundamental Safety Principles, No SF-1, 2006.
- GIF RSWG, Basis for the Safety Approach for Design and Assessment of Generation IV Nuclear Systems Revision 1, 2008.
- A. Carpignano, S. Beils, S. Dulla, Y. Flauw, D. Gerardin, D. Heuer, D. Lecarpentier, E. Merle, E. Ivanov, V. Tiberi, A. Uggenti, Development on an Integral Safety Assessment Methodology for MSFRs, 2018. Work-Package WP1, Deliverable 1.5, SAMOFAR European H2020 Project, Contract number: 661891.
- GIF RSWG, An Integrated Safety Assessment Methodology (ISAM) for Generation IV Nuclear Systems, 2011 version 1.1.
- E. Wattelle, L. Ammirabile, Proposal for a harmonized European methodology for the safety assessment of innovative reactors with fast neutron spectrum to be built in Europe, in: Work-Package WP3, Delivrable 3.5, SARGEN_IV Project, 2012. Contract number: 295446.
- M. Brovchenko, Etudes preliminaires de surete du reacteur a sels fondus MSFR, PhD Thesis, Grenoble Institute of Technology, France, 2013.
- D. Gerardin, M. Allibert, D. Heuer, A. Laureau, E. Merle-Lucotte, C. Seuvre, Design evolutions of the molten salt fast reactor, in: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), Yekaterinburg, Russia, 2017.
- T. Pinna, et al., Functional Failure Mode and Effect Analysis (FFMEA) for the DEMO Cooling Systems of the WCLL Blanket Model, EuroFUSION Report EFDA_D_2JPQSG V1.0, 2015.
- I.A. Papazoglou, O.N. Aneziris, Master Logic Diagram: method for hazard and initiating event identification in process plants, J. Hazard Mater. A97 (2003) 11-30.
- GIF RSWG, Guidance Document for Integrated Safety Assessment Methodology (ISAM) - (GDI), 2014.
- D. Heuer, E. Merle-Lucotte, M. Allibert, M. Brovchenko, V. Ghetta, P. Rubiolo, Towards the thorium fuel cycle with molten salt fast reactors, Ann. Nucl. Energy 64 (2014) 421-429. https://doi.org/10.1016/j.anucene.2013.08.002
- H. Rouch, O. Geoffroy, P. Rubiolo, A. Laureau, D. Heuer, M. Brovchenko, E. Merle-Lucotte, Preliminary thermal-hydraulic core design of the molten salt fast reactor (MSFR), Ann. Nucl. Energy 64 (2014) 449-456. https://doi.org/10.1016/j.anucene.2013.09.012
- M. Brovchenko, D. Heuer, E. Merle-Lucotte, M. Allibert, V. Ghetta, A. Laureau, P. Rubiolo, Design-related studies for the preliminary safety assessment of the molten salt fast reactor, Nucl. Sci. Eng. 175 (2013) 329-339. https://doi.org/10.13182/NSE12-70
- M. Allibert, D. Gerardin, D. Heuer, E. Huffer, A. Laureau, E. Merle, S. Beils, A. Cammi, B. Carluec, S. Delpech, A. Gerber, E. Girardi, J. Krepel, D. Lathouwers, D. Lecarpentier, S. Lorenzi, L. Luzzi, S. Poumerouly, M. Ricotti, V. Tiberi, Description of Initial Reference Design and Identification of Safety Aspects of the MSFR, 2017. Work-Package WP1, Delivrable 1.1, SAMOFAR European H2020 Project, Contract number: 661891.
- A. Laureau, D. Heuer, E. Merle-Lucotte, P. Rubiolo, M. Allibert, M. Aufiero, Transient coupled calculations of the molten salt fast reactor using the transient fission matrix approach, Nucl. Eng. Des. 316 (2017) 112-124. https://doi.org/10.1016/j.nucengdes.2017.02.022
- Southern Company, Modernization Non -Light Water Reactors Probabilistic Risk Assessment Approach, SC-29980-101 Rev A, 2017.
- D. Heuer, A. Laureau, E. Merle-Lucotte, M. Allibert, D. Gerardin, A starting procedure for the MSFR: approach to criticality and incident analysis, in: International Congress on Advances in Nuclear Power Plants (ICAPP'2017), Kyoto, Japan, 2017.
-
P.N. Haubenreich, J.R. Engel, C.H. Gabbard, R.H. Guymon, B.E. Prince, Safety Analysis of Operation with
$^{233}U$ , Rapport ORNL-TM-2111, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 1968. - A. Carpignano, et al., Safety issues related to the intermediate heat storage for the EU DEMO, Fusion Eng. Des. 1010-111 (part A) (2016) 135-140. https://doi.org/10.1016/j.fusengdes.2016.01.078
- A.C. Uggenti, D. Gerardin, A. Carpignano, S. Dulla, E. Merle, D. Heuer, A. Laureau, M. Allibert, Preliminary functional safety assessment for molten salt fast reactors in the framework of the SAMOFAR project, in: International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2017), Pittsburgh, USA, 2017.
- E. Clement, Arbre Analyste, 2013. Available from: http://www.arbre-analyste.fr/.
- T. Pinna, et al., Identification of accident sequences for the DEMO plant, Fusion Eng. Des. 124 (2017) 1277-1280. https://doi.org/10.1016/j.fusengdes.2017.02.026
- Argonne National Laboratory, Uncertainty in Unprotected Loss-of-Heat-Sink, Loss-of-Flow, and Transient-Overpower Accidents, Technical report, Advanced Fuel Cycle Initiative, 2007.
- IRSN, Research and Development with Regard to Severe Accidents in Pressurized Water Reactors: Summary and Outlook, 2007.
피인용 문헌
- Design and neutronic analysis of the intermediate heat exchanger of a fast-spectrum molten salt reactor vol.53, pp.7, 2021, https://doi.org/10.1016/j.net.2021.01.021