Rejuvenation of spent fuel in the force-free helical reactor (FFHR)

Annals of Nuclear Energy

Volumn 32, Issue 4, 2005, Pages 435-454

  Yapici, Hüseyin ^a   Gökçek, Murat ^b  

^a ERCIYES UNIVERSITY   (Turkey)

^b YILDIZ TECHNICAL UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

FISSION REACTIONS; FUSION REACTIONS; HELIUM; LIGHT WATER REACTORS;

ATOMIC DENSITY; FORCE-FREE HELICAL REACTOR (FFHR); OPERATION PERIOD (OP); REJUVENATION;

SPENT FUELS;

TRITIUM;

EID: 12444293884     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2004.10.003     Document Type: Article

References (29)

1. AECL, 1979. Data Base for a CANDU-PHWR operating on a once-through natural uranium cycle (AECL-6593), Atomic Energy of Canada Limited
2. D.H. Berwald Fission Suppressed Hybrid Reactor Fusion Breeder 1982 Lawrence Livermore National Laboratory UCID-19327
3. L.V. Blinkin, and M.V. Novikov Optimal Symbiotic Molten Salt Fission-Fusion System 1977 Kurchatov Institute of Atomic Energy Moscow 1 AE-2819, UCRL-Trans-11288
4. G.L. Brooks Advances in commercial heavy water reactor power stations Transactions of the American Nuclear Society 56 1988 41
5. FFHR Group A. Sagara, O. Motojima, K. Watanabe, S. Imagawa, H. Yamanishi, T. Satow, and H. Tikaraishi Blanket and divertor design for force free helical reactor (FFHR) Fusion Engineering and Design 29 1995 51
6. FFHR Group A. Sagara, O. Motojima, O. Mitarai, S. Imagawa, K. Watanabe, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, N. Noda, T. Noda, N. Ohyabu, T. Satow, A.A. Shishkin, S. Tanaka, T. Terai, K. Yamazaki, and J. Yamamoto Blanket design using FLiBe in helical-type fusion reactor FFHR Journal of Nuclear Materials 248 1997 147
7. FFHR Group H. Yamanishi, A. Sagara, O. Motojima, T. Noda, S. Tanaka, T. Terai, and T. Uda Design studies on nuclear properties on the Flibe blanket for helical-type fusion reactor FFHR Fusion Engineering and Design 41 1998 583
8. FFHR Group T. Uda, A. Sagara, O. Motojima, H. Yamanishi, S. Tanaka, T. Terai, and T. Noda Study of safety concept for a helical-type fusion reactor FFHR Fusion Engineering and Design 42 1998 115
9. Greene, N.M., Arwood, J.W., Wright, R.Q. Parks, C.V., 1994. 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 Lab
10. Greene, N.M., Petrie, L.M. 1997. XSDRNPM-S: A One-Dimensional Discrete-Ordinates Code for Transport Analysis. Sect. F3 of SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/V2/R5), vols. I, II, and III. Version 4.3 of the code package is available from Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory as CCC-545
11. E. Greenspan Fusion-fission hybrid reactors J. Lewins M. Becker Advances in Science and Technology 16 1984 Plenum Press New York 289
12. IAEA, 1979. Status and prospects of thermal breeders and their effects on fuel utilization. Technical report series no. 195. International Atomic Energy Agency, Vienna
13. Lee, J.D. et al., 1982. Feasibility study of a fission-suppressed tandem-mirror hybrid reactor fusion breeder, Lawrence Livermore National Laboratory, CA, UCID-19327
14. R.D. Leggert, and R.P. Omberg Mixed oxide fuel development Proceedings of the International Conference in Fast Breeder Systems: Experience Gained and Path to Economical Power Generation 1987 American Nuclear Society Richland, WA 13-17 September
15. B. Manson, H.P. Thomas, and W.L. Hans Nuclear Chemical Engineering 1981 McGraw-Hill New York
16. R.W. Moir Tandem Mirror Hybrid Reactor Design Study, Annual Report 1979 Lawrence Livermore Laboratory UCRL-52875
17. Mynat, F. R., 1977. Analysis of acceleration breeder concepts with LMFBR, GCFF and Molten Salt Type Blankets, In: Proc. Information Mtg. Accelerator Breeding, Upton, January 18-19. NewYork
18. 2 molten salt mixture Journal of Nuclear Materials 283-287 2000 1326
19. Raghep, M.H. et al., 1979. Nuclear performance of molten salt fusion-fission symbiotic system for catalyzed D-D and D-T reactors. ORNL-TM-6560, Oak Ridge National Laboratory
20. A. Sagara, O. Motojima, S. Imagawa, O. Mitarai, T. Noda, T. Uda, K. Watanabe, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, N. Noda, N. Ohyabu, T. Satow, A.A. Shishkin, S. Dai-Kai, A. Suzuki, S. Tanaka, T. Terai, K. Yamazaki, and J. Yamamoto Design studies of helical-type fusion reactor FFHR Fusion Engineering and Design 41 1998 349
21. A. Sagara, T. Muroga, O. Motojima, T. Noda, S. Tanaka, T. Terai, A. Kohyama, and H. Matsui Materials design and related R&D issues for the force-free helical reactor FFHR Journal of Nuclear Materials 258-263 1998 2079
22. A. Sagara, H. Yamanishi, S. Imagawa, T. Muroga, T. Uda, T. Noda, S. Takahashi, K. Fukumoto, T. Yamamoto, H. Matsui, A. Kohyama, H. Hasizume, S. Toda, A. Shimizu, A. Suzuki, Y. Hosoya, S. Tanaka, T. Terai, S. Dai-Kai, and O. Motojima Design and development of the flibe blanket for helical-type fusion reactor FFHR Fusion Engineering and Design 49-50 2000 661
23. E. Teller Fusion Magnetic Confinement. Part B 1 1981 Academic Press New York
24. A.E. Waltar, and L.W. Deitrich Status of research on key LMR safety issues Nuclear Safety 29 2 1988 125
25. H. YapIcI XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data 2001 Erciyes University Turkey
26. H. YapIcI Study on transmutation of minor actinides discharged from high burn-up PWR-MOX spent fuel in the force-free helical reactor Annals of Nuclear Energy 30 2003 413 436
27. H. YapIcI Determination of the optimal plutonium fraction in transuranium discharged from pressured water reactor (PWR) spent fuel for a flat fission power generation in the force-free helical reactor (FFHR) along the transmutation period Annals of Nuclear Energy 30 2003 633 649
28. 2 spent fuel and power flattening along the operation period in the force-free helical reactor Energy Conversion and Management 44 2003 2893 2913
29. H. YapIcI Study of fissile fuel breeding concept for the force-free helical reactor Fusion and Engineering Design 65 2003 599 609