Study of fissile fuel breeding concept for the force-free helical reactor

Fusion Engineering and Design

Volumn 65, Issue 4, 2003, Pages 599-609

  Yapici, Hüseyin ^a  

^a ERCIYES UNIVERSITY   (Turkey)

Author keywords

Curium oxide; Fissile fuel breeding; Force free helical reactor

Indexed keywords

BORON COMPOUNDS; CURIUM; INCINERATION; NEUTRONS; NUMERICAL METHODS; PRESSURIZED WATER REACTORS; REACTOR SHIELDING; SPENT FUELS;

FORCE-FREE HELICAL REACTORS (FFHR);

FUSION REACTORS;

EID: 0042525706     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(03)00049-8     Document Type: Article

References (44)

1. Teller E. Fusion Magnetic Confinement. Part B. 1:1981;Academic Press.
2. L.V. Blinkin, M.V. Novikov, Optimal Symbiotic Molten Salt Fission-Fusion System, Kurchatov Institute of Atomic Energy, 1 AE-2819, Moscow, UCRL-Trans-11288, 1977.
3. F.R. Mynat, Analysis of Acceleration Breeder Concepts with LMFBR, GCFF and Molten Salt Type Blankets, Proceedings of the Information Mtg. Accelerator Breeding, Upton, New York, 18-19 January 1977.
4. R.W. Moir (Ed.), Tandem Mirror Hybrid Reactor Design Study, Annual Report, Lawrence Livermore Laboratory, UCRL-52875, 1979.
5. M.M.H. Raghep, R.T Sontoro, J.M. Barnes, M.J. Saltmarsh, Nuclear Performance of Molten Salt Fusion-Fission Symbiotic System for Catalyzed DD and DT Reactors, ORNL-TM-6560, 1979.
6. D.H. Berwald, J.A. Maniscalco, J.D. Lee, R.W. Moir, Fission Suppressed Tandem Mirrow Hybird Reactor Options. NTIS CONF-801011, VS, (1981) 1465.
7. Greenspan E. Lewins J., Becker M. Fusion-Fission Hybrid Reactors, Advances in Science and Technology. 16:1984;289 Plenum Press.
8. J.D. Lee, R.W. Moir, W.L. Barr, Feasibility Study of a Fission-Suppressed Tandem-Mirror Hybrid Reactor. ORNL UCID-19327 (1982).
9. Şahin S., Yapici H., Baltacioglu E. Fusion breeder with enhanced safeguarding capabilities against nuclear weapon proliferation. Energy Conversion and Management. 39:1998;899.
10. Şahin S., Yapici H. Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation. Annals of Nuclear Energy. 26:1999;13.
11. Şahin S., Özceyhan V., Yapici H. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel. Annals of Nuclear Energy. 28:2001;203.
12. Şahin S., Yapici H., Şahin N. Neutronic performance of proliferation hardened thorium fusion breeders. Fusion Engineering and Design. 54:2001;63.
13. Şahin S., Yapici H. Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel. Fusion Technology. 16:1989;331.
14. Şahin S., Baltacioglu E., Yapici H. Potential of a catalysed fusion driven hybrid reactor for the regeneration of CANDU spent fuel. Fusion Technology. 20:1991;26.
15. Şahin S., Yapici H., Baltacioglu E. Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket. Kerntechnik. 59:1994;270.
16. Şahin S., Yapici H. Rejuvenation of LWR fuel in fusion blankets. Annals of Nuclear Energy. 25:1998;1317.
17. Şahin S., Yapici H., Bayrak M. Spent mixed oxide fuel rejuvenation in fusion breeders. Fusion and Engineering Design. 47:1999;9.
18. Şahin S. Power flattening in a catalyzed (D,D) fusion driven hybrid blanket using nuclear waste actinides. Nuclear Technology. 92:1999;93.
19. Yapici H., Çürüttü İ., Özceyhan V., Kirbiyik M. Potential of a fusion-fission hybrid reactor using various coolants to breed fissile fuel for LWRs. Annals of Nuclear Energy. 26:1999;821.
20. 2) and different for various volume fraction. Annals of Nuclear Energy. 27:1999;279.
21. Yapici H., Akansu S.O., Özceyhan V. Neutronic analysis of a moderated (D,T) fusion driven hybrid blanket. Annals of Nuclear Energy. 27:2000;1237.
22. Yapici H., Şahin N., Bayrak M. Investigation of neutronic potential of a moderated (D-T) fusion driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs. Energy Conversion and Management. 41:2000;435.
23. f/SiC. Annals of Nuclear Energy. 29:2002;1389.
24. Huang J.H., Qiu L.J. Joint design team of SWIP and ASIPP, detailed conceptual design of the fusion experimental breeder. Fusion Engineering and Design. 41:1998;597.
25. Taczanowski S., Domańska G., Cetnar J. Fusion-driven transmutations of nuclear waste - a misconception or an incentive for promotion of fusion energy. Fusion Engineering and Design. 41:1998;455.
26. Chen Y., Wu Y. Conceptual study on high performance blanket in a spherical tokamak fusion-driven transmuter. Fusion Engineering and Design. 49-50:2000;507.
27. Feng K.M. Activation calculation and waste management for a fusion experimental breeder, FEB-E. Fusion Engineering and Design. 51-52:2000;505.
28. David S., Billebaud A., Brandan M.E., Brissot R., Giorni A., Heuer D., Loiseaux J.-M., Méplan O., Nifenecker H., Viano J.-B., Schapira J.-P. Fast subcritical hybrid reactors for energy production: evolution of physical parameters and induced radiotoxicities. Nuclear Instruments and Methods in Physics Research A. 443:2000;510.
29. Yapici H., Übeyli M., Yalçin S. Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium. Annals of Nuclear Energy. 29:2002;1871.
30. Sagara A., Motojima O., Watanabe K., Imagawa S., Yamanishi H., Satow T., Tikaraishi H. Blanket and divertor design for force free helical reactor (FFHR). Fusion Engineering and Design. 29:1995;51.
31. Sagara A., Motojima O., Mitarai O., Imagawa S., Watanabe K., Yamanishi H., Chikaraishi H., Kohyama A., Matsui H., Muroga T., Noda N., Noda T., Ohyabu N., Satow T., Shishkin A.A., Tanaka S., Terai T., Yamazaki K., Yamamoto J. Blanket design using FLiBe in helical-type fusion reactor FFHR. Journal of Nuclear Materials. 248:1997;147.
32. Sagara A., Motojima O., Imagawa S., Mitarai O., Noda T., Uda T., Watanabe K., Yamanishi H., Chikaraishi H., Kohyama A., Matsui H., Muroga T., Noda N., Ohyabu N., Satow T., Shishkin A.A., Dai-Kai S., Suzuki A., Tanaka S., Terai T., Yamazaki K., Yamamoto J. Design studies of helical-type fusion reactor FFHR. Fusion Engineering and Design. 41:1998;349.
33. Yamanishi H., Sagara A., Motojima O., Noda T., Tanaka S., Terai T., Uda T. Design studies on nuclear properties on the Flibe blanket for helical-type fusion reactor FFHR. Fusion Engineering and Design. 41:1998;583.
34. Uda T., Sagara A., Motojima O., Yamanishi H., Tanaka S., Terai T., Noda T. Study of safety concept for a helical-type fusion reactor, FFHR. Fusion Engineering and Design. 42:1998;115.
35. Sagara A., Muroga T., Motojima O., Noda T., Tanaka S., Terai T., Kohyama A., Matsui H. Materials design and related R&D issues for the force-free helical reactor (FFHR). Journal of Nuclear Materials. 258-263:1998;2079.
36. Nishimura H., Terai T., Yoneoka T., Tanaka S., Sagara A., Motojima O. Compatibility of structural candidate materials with LiF-BeF2 molten salt mixture. Journal of Nuclear Materials. 283-287:2000;1326.
37. Sagara A., Yamanishi H., Imagawa S., Muroga T., Uda T., Noda T., Takahashi S., Fukumoto K., Yamamoto T., Matsui H., Kohyama A., Hasizume H., Toda S., Shimizu A., Suzuki A., Hosoya Y., Tanaka S., Terai T., Dai-Kai S., Motojima O. Design and development of the flibe blanket for helical-type fusion reactor FFHR. Fusion Engineering and Design. 49-50:2000;661.
38. N.M. Greene, L.M. Petrie, XSDRNPM-S: a One-Dimensional Discrete-Ordinates Code for Transport Analysis, Sect. F3 of SCALE.
39. SCALE: a Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), vols. I, II and III, May 2000. Version 4.4a of the code package is available from Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory as CCC-545.
40. N.M. Greene, J.W. Arwood, R.Q. Wright, C.V. Parks, The LAW Library - a Multi Group Cross-Section Library for Use in Radioactive Waste Analysis Calculations, ORNL/TM-12370, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, 1994.
41. N.F. Landers, L.M. Petrie, CSAS, Control Module For Enhanced Criticality Safety Analysis Sequences, vol. I, Sect. C4, of SCALE.
42. N.M. Greene, L.M. Petrie, R.M. Westfall, NITAWL-II: SCALE System Module for Performing Resonance Shielding and Working Library Production, vol. II, Sect. F2 of SCALE..
43. N.M. Greene, BONAMI-S: Resonance Self-Shielding by the Bondarenko Method, Sect. F1 of SCALE.
44. Yapici H. XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data. 2001;Erciyes University, Turkey.