Neutronics assessment of molten salt breeding blanket design options

Fusion Science and Technology

Volumn 47, Issue 3, 2005, Pages 510-517

  Sawan, M E ^a   Malang, S ^b   Wong, C P C ^c   Youssef, M Z ^d  

^a UNIVERSITY OF WISCONSIN MADISON   (United States)

^b Fusion Nuclear Technology Consulting   (Germany)

^c GENERAL ATOMICS   (United States)

^d UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FUSION REACTIONS; HEAT FLUX; MELTING; NEUTRONS; NUCLEAR POWER PLANTS; SALTS; TRITIUM; VISCOSITY;

MELTING POINT; MOLTEN SALT; NEUTRONICS; STRUCTURE TEMPERATURE;

BREEDER REACTORS;

EID: 17544372895     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST05-A735     Document Type: Conference Paper

References (20)

1. M.A. ABDOU et al., "On the Exploration of Innovative Concepts for Fusion Chamber Technology," Fusion Engineering & Design, 54, 181 (2001).
2. A. SAGARA et al., "Studies on Flibe Blanket Designs in Helical Reactor FFHR," Fusion Technology, 39, 153 (2001).
3. M. SAWAN and D.-K. SZE, "Transmutation and Production Rates of Elements in Flibe and Flinabe with Impact on Chemistry Control," Fusion Science & Technology, 44, 64 (2003).
4. R. NYGREN et al., "A Fusion Reactor Design with a Liquid First Wall and Divertor," To be Published in Fusion Engineering & Design (2004).
5. J. MCDONALD et al., "Measurement of the Melting Point Temperature of Several Lithium-Sodium-Beryllium Fluoride Salt (Flinabe) Mixtures," These Proceedings.
6. M. YOUSSEF, M. SAWAN, and D.-K. SZE, "The Breeding Potential of Flinabe and Comparison to Flibe in CLiFF High Power Density Concept," Fusion Engineering & Design, 61-62, 497 (2002).
7. nd Symposium on Fusion Technology, Helsinki, Finland, September 9-13, 2002.
8. C. WONG et al., "Molten Salt Self-Cooled Solid First Wall and Blanket Design Based on Advanced Ferritic Steel," To be Published in Fusion Engineering & Design (2004).
9. C. WONG et al., "Assessment of Liquid Breeder First Wall and Blanket Options for the DEMO Design," These Proceedings.
10. F. NAJMABADI et al., "Overview of ARIESRS Tokamak Fusion Power Plant," Fusion Engineering & Design, 41, 365 (1998).
11. D-K. SZE, M. TILLACK, and L. EL-GUEBALY, "Blanket System Selection for the ARIES-ST," Fusion Engineering & Design, 48, 371 (2000).
12. P. NORAJITRA et al., "The Second Advanced Lead Lithium Blanket Concept Using ODS Steel as Structural Material and SiC/SiC Flow Channel Inserts as Electrical and Thermal Insulators," FZKA-6385, Forschungszentrum Karlsruhe (1999).
13. R.E. ALCOUFFE et al., "DANTSYS 3.0, A Diffusion Accelerated Neutral Particle Transport Code System," LA-12969-M, Los Alamos National Laboratory (June 1995).
14. M. HERMAN and H. WIENKE, "FENDL/MG-2.0 and FENDL/MC-2.0, The Processed Cross-Section Libraries For Neutron-Photon Transport Calculations," Report IAEA-NDS-176, Rev. 3, International Atomic Energy Agency (October 1998).
15. BALDWIN et al., "Tritium Release from Be," Journal of Nuclear Materials, 212-215, 948 (1994).
16. ANDREEV et al., "Tritium Release from Be," Journal of Nuclear Materials, 237-244, 880 (1996).
17. B. J. MERRILL, M. SAWAN, C.P.C. WONG et al., "Safety Assessment of Two Advanced Ferritic Steel Molten Salt Blanket Design Concepts," To be Published in Fusion Engineering and Design (2004).
18. M. SAWAN AND P. WALSTROM, "Superconducting Magnet Radiation Effects in Fusion Reactors," Fusion Technology, 10/3, 741 (1986).
19. R. KLUEH et al., "Microstructure and Mechanical Properties of Oxide-Dispersion-Strengthened Steels," Fusion Materials Semiannual Progress Report for the Period Ending June 30, 2000 (DOE/ER-0313/28), pp. 123-130 (2000).
20. X-5 MONTE CARLO TEAM, Ed., "MCNP-A General Monte Carlo N-Particle Transport Code, Version 5- Volume II: Users Guide," LA-CP-03-0245, Los Alamos National Laboratory (April 2003).