Analysis on the neutron kinetics for a molten salt reactor

Progress in Nuclear Energy

Volumn 51, Issue 4-5, 2009, Pages 624-636

  Zhang, D L ^a   Qiu, S Z ^a   Su, G H ^a   Liu, C L ^a   Qian, L B ^a  

^a XI'AN JIAOTONG UNIVERSITY   (China)

Author keywords

Inlet temperature drop; Molten salt reactor; Neutron kinetics; Pump coastdown; Rods drop

Indexed keywords

DIFFUSION; DROPS; FUSED SALTS; HEAT TRANSFER; MOLTEN MATERIALS; NEUTRON BEAMS; NEUTRON FLUX; PUMPS;

ANALYSIS METHODS; BALANCE EQUATIONS; CONVECTION DIFFUSIONS; CONVENTIONAL REACTORS; DELAYED NEUTRON PRECURSORS; FUEL SALT FLOWS; GROUP CONSTANTS; HEAT TRANSFER MODELS; IMPLICIT SCHEMES; INLET TEMPERATURE DROP; KINETIC MODELS; MATHEMATICAL EQUATIONS; MOLTEN SALT REACTOR; NEUTRON DIFFUSION EQUATIONS; NEUTRON DIFFUSIONS; NEUTRON KINETICS; POWER LAWS; RODS DROP; SOLID FUELS; TEMPERATURE FEEDBACKS; THERMAL-NEUTRON FLUXES; TIME DEPENDENTS; TRANSIENT CONDITIONS;

NUCLEAR REACTORS;

EID: 63349091169     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2008.11.008     Document Type: Article

References (14)

1. Dulla S., Ravetto P., and Rostagno M.M. Neutron kinetics of fluid-fuel systems by the quasi-static method. Ann. Nucl. Energy 31 (2003) 1709
2. IAEA, 2007. The basic nuclear data file is available on-line at the website: http://www-nds.iaea.org.
3. Ignatiev V., Feynberg O., and Myasnikov A. Neutronic properties and possible fuel cycle of a molten salt transmuter. Proceedings of the 2003 ANS/ENS International Winter Meeting (GLOBAL 2003) (16-20 November 2003), Hyatt Regency, New Orleans, LA, USA
4. Krepel J., Grundmann U., and Rohde U. DYN1D-MSR dynamics code for molten salt reactors. Ann. Nucl. Energy 32 (2005) 1799
5. Krepel J., Grundmann U., and Rohde U. DYN3D-MSR spatial dynamics code for molten salt reactors. Ann. Nucl. Energy 34 (2007) 449
6. Lapenta G., Mattioda F., and Ravetto P. Point kinetic model for fluid fuel systems. Ann. Nucl. Energy 28 (2000) 1759
7. Liao C.K. Steady on Numerical Method for Three Dimensional Nodal Space-Time Neutron Kinetic Equations and Coupled Neutronic/Thermal-Hydraulic Core Transient Analysis (2002), Xi'an Jiaotong University
8. Marleau G., Hebert A., and Roy R. A User's Guide for DRAGON. Technical Report, Report IGE-174 (1996), Ecole Polytechnique de Montreal, Canada
9. Mitachi K., Yamana Y., and Suzuki T. Neutronic Examination on Plutonium Transmutation by a Small Molten-Salt Fission Power Station (1995) Technical Report [R], IAEA-TECDOC-840
10. Most Project. Molten salt reactor technology phase 1. Proceedings of the 5th Framework Programme of European Commission, October 2001-December 2003 (2004)
11. Nicolino C., Lapenta G., and Dulla S. Coupled dynamics in the physics of molten salt reactors. Ann. Nucl. Energy 35 (2008) 314
12. Tao W.Q. Numerical Heat Transfer. second ed. (2004), Xi'an Jiaotong University Press, Xi'an
13. Xie Z.S. Nuclear Physics Analysis (2004), Xi'an Jiaotong University Press, Xi'an
14. Yamamoto T., Mitachi K., and Ikeuchi K. Transient characteristics of small molten salt reactor during blockage accident. Heat Transfer Asian Res. 35 (2006) 434