Improvements and validation of the transient analysis code MOREL for molten salt reactors

References

• Pioro IL. Handbook of generation IV nuclear reactors. Cambridge (UK): Woodhead Publishing; 2016.
   Google Scholar
• John EK. Generation IV international forum: a decade of progress through international cooperation. Prog Nucl Energy. 2014;77:240–246.
   Web of Science ®Google Scholar
• Abram T, Ion S. Generation-IV nuclear power: a review of the state of the science. Energy Policy. 2008;36:4323–4330.
   Web of Science ®Google Scholar
• Haubenreich PN, Engel JR, Prince BE, et al. MSRE design and operations report, part III, nuclear analysis. Oak Ridge (TN): Oak Ridge National Laboratory; 1964. ( ORNL-TM-730).
   Google Scholar
• Hugo VD. Delayed neutron effectiveness in a fluidized bed fission reactor. Ann Nucl Energy. 1996;23:41–46.
   Web of Science ®Google Scholar
• Kophazi J, Szieberth M, Feher S. MCNP-based calculation of reactivity loss in circulating fuel reactors. Proceedings of the International Conference on Nuclear Mathematical and Computational Sciences: A Century in Review-A Century Anew; 2003 April 6–10; Gatlinburg, TN.
   Google Scholar
• Serp J, Allibert M, Beneš O, et al. The molten salt reactor (MSR) in generation IV: overview and perspectives. Prog Nucl Energy. 2014;77:308–319.
   Web of Science ®Google Scholar
• Wang S, Rineiski A, Maschek W. Molten salt related extensions of the SIMMER-III code and its application for a burner reactor. Nucl Eng Des. 2006;236:1580–1588.
   Web of Science ®Google Scholar
• Křepel U, Grundmann J, Rohde U, et al. DYN1D MSR dynamics code for molten salt reactors. Ann Nucl Energy. 2005;32:1799–1824.
   Web of Science ®Google Scholar
• Křepel J, Rohde U, Grundmann U, et al. DYN3D MSR spatial dynamics code for molten salt reactors. Ann Nucl Energy. 2007;34:449–462.
   Web of Science ®Google Scholar
• Lecarpentier D, Carpentier V. A neutronics program for critical and nonequilibrium study of mobile fuel reactors: the Cinsf1D code. Nucl Sci Eng. 2003;143:33–46.
   Web of Science ®Google Scholar
• Guo ZP, Zhou JJ, Zhang DL, et al. Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor. Nucl Eng Des. 2013;258:144–156.
   Web of Science ®Google Scholar
• Dulla S, Ravetto P, Rostagno MM. Neutron kinetics of fluid-fuel systems by the quasi-static method. Ann Nucl Energy. 2004;31:1709–1733.
   Web of Science ®Google Scholar
• Zhang DL, Qiu SZ, Su GH, et al. Development of a steady state analysis code for a molten salt reactor. Ann Nucl Energy. 2009;36:590–603.
   Web of Science ®Google Scholar
• Zhang DL, Qiu SZ, Su GH, et al. Analysis on the neutron kinetics for a molten salt reactor. Prog Nucl Energy. 2009; 51:624–636.
   Web of Science ®Google Scholar
• Zhuang K, Cao LZ, Zheng YQ, et al. Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design. Nucl Sci Technol. 2014; 52:251–263.
   Web of Science ®Google Scholar
• Li YZ. Advanced reactor core neutronics computational algorithms based on the variational nodal and nodal SP3 methods [Doctoral dissertation]. Xi'an (China): Xi'an Jiaotong University; 2012.
   Google Scholar
• Stamm'ler RJJ. HELIOS methods. In: Program manual rev. 3, program HELIOS-1.5. Waltham (MA): Studsvik Scandpower; 1998. p. IX–1.
   Google Scholar
• Shim CB, Jung YS, Joo HG, et al. Application of backward differentiation formula to spatial reactor kinetics calculation with adaptive time step control. Nucl Eng Technol. 2011; 43(6):531–546.
   Web of Science ®Google Scholar
• Hoffman A. A time-dependent method of characteristics formulation with time derivative propagation [Doctoral dissertation]. Ann Arbor (MI): University of Michigan; 2013.
   Google Scholar
• Henry AF. Nuclear-reactor analysis. Cambridge (MA): MIT Press; 1975.
   Google Scholar
• Akcasu Z, Lellouche GS, Shotkin LM. Mathematical methods in nuclear reactor dynamics. New York (NY): Academic Press; 1971.
   Google Scholar
• Lapenta G, Ravetto P, Ritter G. Effective delayed neutron fraction for fluid-fuel systems. Ann Nucl Energy 2000;27:1523–1532.
   Web of Science ®Google Scholar
• Dulla S, Mund E, Ravetto P. The quasi-static method revisited. Prog Nucl Energy 2008; 50:908–920.
   Web of Science ®Google Scholar
• Hu TL, Wu HC, Cao LZ, et al. [Neutronics and thermal-hydraulics coupling analysis of molten salt reactor at steady state]. At Energy Sci Technol. 2016;50:1823–1827. Chinese.
   Google Scholar
• Prince VE, Ball SJ, Engel JR. Zero-power physics experiments on molten-salt reactor experiment. Oak Ridge (TN): Oak Ridge National Laboratory; 1968. ( ORNL-4233).
   Google Scholar
• Křepel J. Dynamics of molten salt reactors [Doctoral dissertation]. Prague (Czech Republic): Czech Technical University in Prague; 2006.
   Google Scholar
• Rosenthal MW. Molten-salt reactor program semi-annual progress report for period ending February 28 1969. Oak Ridge (TN): Oak Ridge National Laboratory; 1969. ( ORNL-4396).
   Google Scholar
• Delpech M, Dulla S, Garzenne C, et al. Benchmark of dynamic simulation tools for molten salt reactors. International Conference GLOBAL 2003; 2003 Nov; New Orleans, LA.
   Google Scholar
• Engel JR, Haubenreich PN. Temperature in the MSRE core during steady-state power operation. Oak Ridge (TN): Oak Ridge National Laboratory; 1962. ( ORNL-TM-378).
   Google Scholar