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Volumn 35, Issue 3, 1999, Pages 309-353

New approach for assessing the required tritium breeding ratio and startup inventory in future fusion reactors

Author keywords

[No Author keywords available]

Indexed keywords

BREEDER REACTORS; COMPUTER SIMULATION; NUCLEAR FUELS; REACTOR STARTUP; TRITIUM;

EID: 0032647333     PISSN: 07481896     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST99-A84     Document Type: Article
Times cited : (39)

References (35)
  • 2
    • 0344090882 scopus 로고
    • Breeding ratio, inventory, and doubling time in a D-T fusion reactor
    • W. F. VOGELSANG, "Breeding Ratio, Inventory, and Doubling Time in a D-T Fusion Reactor," Nucl. Technol., 15, 470 (1972).
    • (1972) Nucl. Technol. , vol.15 , pp. 470
    • Vogelsang, W.F.1
  • 3
    • 0020809776 scopus 로고
    • Analysis of the tritium requirements for a power reactor
    • F. CARRÉ, E. PROUST, and A. ROCABOY, "Analysis of the Tritium Requirements for a Power Reactor," Nucl. Technol./ Fusion, 4, 2, Part 2, 93 (1983).
    • (1983) Nucl. Technol./ Fusion , vol.4 , Issue.2 PART 2 , pp. 93
    • Carré, F.1    Proust, E.2    Rocaboy, A.3
  • 4
    • 0022681014 scopus 로고
    • An assessment of tritium breeding requirements based on the tritium fuel cycle
    • J. JUNG, "An Assessment of Tritium Breeding Requirements Based on the Tritium Fuel Cycle," Fusion Technol., 9, 308 (1986).
    • (1986) Fusion Technol. , vol.9 , pp. 308
    • Jung, J.1
  • 5
    • 0030074139 scopus 로고    scopus 로고
    • Requirements of tritium breeding ratio for early fusion power reactors
    • Y. ASAOKA, K. OKANO, T. YOSHIDA, and K. TOMABECHI, "Requirements of Tritium Breeding Ratio for Early Fusion Power Reactors," Fusion Technol., 30, 3, Part 2A, 853 (1996).
    • (1996) Fusion Technol. , vol.30 , Issue.3 PART 2A , pp. 853
    • Asaoka, Y.1    Okano, K.2    Yoshida, T.3    Tomabechi, K.4
  • 6
    • 0005962605 scopus 로고
    • Time-dependent tritium inventories and flow rates in fuel cycle components of a tokamak fusion reactor
    • W. KUAN, M. A. ABDOU, and R. S. WILLMS, "Time-Dependent Tritium Inventories and Flow Rates in Fuel Cycle Components of a Tokamak Fusion Reactor," Fusion Eng. Des., 28, 329 (1995).
    • (1995) Fusion Eng. Des. , vol.28 , pp. 329
    • Kuan, W.1    Abdou, M.A.2    Willms, R.S.3
  • 7
    • 0029392783 scopus 로고
    • Dynamic simulation of a proposed ITER tritium processing system
    • W. KUAN, R. S. WILLMS, and M. A. ABDOU, "Dynamic Simulation of a Proposed ITER Tritium Processing System," Fusion Technol., 28, 3, Part 1, 664 (1995).
    • (1995) Fusion Technol. , vol.28 , Issue.3 PART 1 , pp. 664
    • Kuan, W.1    Willms, R.S.2    Abdou, M.A.3
  • 8
    • 0029391697 scopus 로고
    • An investigation of plasma-facing component material-effects on tritium reprocessing systems
    • W. KUAN and M. A. ABDOU, "An Investigation of Plasma-Facing Component Material-Effects on Tritium Reprocessing Systems," Fusion Technol., 28, 3, Part 1, 658 (1995).
    • (1995) Fusion Technol. , vol.28 , Issue.3 PART 1 , pp. 658
    • Kuan, W.1    Abdou, M.A.2
  • 9
    • 0029459938 scopus 로고
    • Simplified fuel cycle tritium inventory model for systems studies - An illustrative example with an optimized cryopump exhaust system
    • Champaign, Illinois, September 30-October 5
    • W. KUAN and S. K. HO, "Simplified Fuel Cycle Tritium Inventory Model for Systems Studies - An Illustrative Example with an Optimized Cryopump Exhaust System," Proc. 16th IEEE/NPSS Symp. Fusion Engineering, Champaign, Illinois, September 30-October 5, 1995.
    • (1995) Proc. 16th IEEE/NPSS Symp. Fusion Engineering
    • Kuan, W.1    Ho, S.K.2
  • 10
    • 0344952883 scopus 로고    scopus 로고
    • CFTSIM-ITER dynamic fuel cycle model
    • Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, (in press)
    • A. BUSIGIN and P. GIERSZEWSKI, "CFTSIM-ITER Dynamic Fuel Cycle Model," Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, 1997, Fusion Eng. Des. (in press).
    • (1997) Fusion Eng. Des.
    • Busigin, A.1    Gierszewski, P.2
  • 11
    • 0029391838 scopus 로고
    • Steady state and dynamic simulation of the ITER hydrogen isotope separation system
    • A. BUSIGIN and S. K. SOOD, "Steady State and Dynamic Simulation of the ITER Hydrogen Isotope Separation System," Fusion Technol., 28, 3, Part 1, 544 (1995).
    • (1995) Fusion Technol. , vol.28 , Issue.3 PART 1 , pp. 544
    • Busigin, A.1    Sood, S.K.2
  • 12
    • 0029391681 scopus 로고
    • Modeling tritium processes in plasma-facing beryllium
    • G. R. LONGHURST, R. A. ANDERL, T. J. DOLAN, and M. J. MULOCK, "Modeling Tritium Processes in Plasma-Facing Beryllium," Fusion Technol., 28, 3, Part 1, 1217 (1995).
    • (1995) Fusion Technol. , vol.28 , Issue.3 PART 1 , pp. 1217
    • Longhurst, G.R.1    Anderl, R.A.2    Dolan, T.J.3    Mulock, M.J.4
  • 13
    • 8544279990 scopus 로고    scopus 로고
    • Assessment of erosion and surface tritium inventory issues for the ITER divertor
    • J. N. BROOKS, R. CAUSEY, G. FEDERICI, and D. N. RUZIC, "Assessment of Erosion and Surface Tritium Inventory Issues for the ITER Divertor," J. Nucl. Mater., 241-243, 294 (1997).
    • (1997) J. Nucl. Mater. , vol.241-243 , pp. 294
    • Brooks, J.N.1    Causey, R.2    Federici, G.3    Ruzic, D.N.4
  • 14
    • 0028494656 scopus 로고
    • An assessment of models for tritium release from ceramic breeders for blanket analysis applications
    • G. FEDERICI, A. R. RAFFRAY, M. C. BILLONE, C. H. WU, S. CHO, and M. A. ABDOU, "An Assessment of Models for Tritium Release from Ceramic Breeders for Blanket Analysis Applications," J. Nucl. Mater., 212-215, 1003 (1994).
    • (1994) J. Nucl. Mater. , vol.212-215 , pp. 1003
    • Federici, G.1    Raffray, A.R.2    Billone, M.C.3    Wu, C.H.4    Cho, S.5    Abdou, M.A.6
  • 15
    • 0012370657 scopus 로고
    • Progress in tritium retention and release modeling for ceramic breeders
    • A. R. RAFFRAY, M. C. BILLONE, G. FEDERICI, and S. TANAKA, "Progress in Tritium Retention and Release Modeling for Ceramic Breeders," Fusion Eng. Des., 28, 240 (1995).
    • (1995) Fusion Eng. Des. , vol.28 , pp. 240
    • Raffray, A.R.1    Billone, M.C.2    Federici, G.3    Tanaka, S.4
  • 17
    • 0345384378 scopus 로고
    • Estimation of the tritium production and inventory in beryllium
    • S. SHIMAKAWA et al., "Estimation of the Tritium Production and Inventory in Beryllium," Fusion Eng. Des., 28, 215 (1995).
    • (1995) Fusion Eng. Des. , vol.28 , pp. 215
    • Shimakawa, S.1
  • 18
    • 0031546516 scopus 로고    scopus 로고
    • The influence of key operation parameters and material properties on the quantification of tritium inventory and permeation in the plasma facing components of ITER
    • G. FEDERICI, D. HOLLAND, G. JANESCHITZ, and C. H. WU, "The Influence of Key Operation Parameters and Material Properties on the Quantification of Tritium Inventory and Permeation in the Plasma Facing Components of ITER," J. Nucl. Mater., 241-243, 260 (1997).
    • (1997) J. Nucl. Mater. , vol.241-243 , pp. 260
    • Federici, G.1    Holland, D.2    Janeschitz, G.3    Wu, C.H.4
  • 19
    • 0346873231 scopus 로고    scopus 로고
    • Tritium inventory in the ITER PFC's: Predictions, uncertainties, R&D status and priority needs
    • Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, (in press)
    • G. FEDERICI et al., "Tritium Inventory in the ITER PFC's: Predictions, Uncertainties, R&D Status and Priority Needs," Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, 1997, Fusion Eng. Des. (in press).
    • (1997) Fusion Eng. Des.
    • Federici, G.1
  • 20
    • 0031643889 scopus 로고    scopus 로고
    • A simplified torus module for use within an integrated dynamic fusion fuel cycle tritium model for ITER
    • San Diego, California, October 6-10
    • W. KUAN, G. FEDERICI, P. GIERSZEWSKI, and M. SUGIHARA, "A Simplified Torus Module for Use Within an Integrated Dynamic Fusion Fuel Cycle Tritium Model for ITER," Proc. 17th IEEE/NPSS Symp. Fusion Engineering, San Diego, California, October 6-10, 1997.
    • (1997) Proc. 17th IEEE/NPSS Symp. Fusion Engineering
    • Kuan, W.1    Federici, G.2    Gierszewski, P.3    Sugihara, M.4
  • 21
    • 38249026653 scopus 로고
    • Tritium supply for near-term fusion devices
    • P. GIERSZEWSKI, "Tritium Supply for Near-Term Fusion Devices," Fusion Eng. Des., 10, 399 (1989).
    • (1989) Fusion Eng. Des. , vol.10 , pp. 399
    • Gierszewski, P.1
  • 22
    • 0344090879 scopus 로고
    • Comparison of tritium production reactors
    • L. J. WITTENBERG, "Comparison of Tritium Production Reactors," Fusion Technol., 19, 3, Part 2a, 1040 (1991).
    • (1991) Fusion Technol. , vol.19 , Issue.3 PART 2A , pp. 1040
    • Wittenberg, L.J.1
  • 23
    • 0026830521 scopus 로고
    • The cost of tritium production in a fusion reactor
    • L. J. WITTENBERG, "The Cost of Tritium Production in a Fusion Reactor," Fusion Technol., 21, 2, Part 2, 886 (1992).
    • (1992) Fusion Technol. , vol.21 , Issue.2 PART 2 , pp. 886
    • Wittenberg, L.J.1
  • 24
    • 0031357864 scopus 로고    scopus 로고
    • Atokamak tritium production reactor
    • W. M. STACEY et al., "ATokamak Tritium Production Reactor," Fusion Technol., 32, 563 (1997).
    • (1997) Fusion Technol. , vol.32 , pp. 563
    • Stacey, W.M.1
  • 25
    • 0031131341 scopus 로고    scopus 로고
    • Comparative availability analysis of the four European DEMO blanket concepts in view of the selection exercise
    • H. SCHNAUDER, C. NARDI, and M. EID, "Comparative Availability Analysis of the Four European DEMO Blanket Concepts in View of the Selection Exercise," Fusion Eng. Des., 36, 343 (1997).
    • (1997) Fusion Eng. Des. , vol.36 , pp. 343
    • Schnauder, H.1    Nardi, C.2    Eid, M.3
  • 26
    • 0029459040 scopus 로고
    • Breeding potential of candidate breeders for the U.S. demo power plant
    • Champaign, Illinois, September 30-October 5, 1995, Institute of Electrical and Electronics Engineers
    • L. A. EL-GUEBALY and the ARIES TEAM, "Breeding Potential of Candidate Breeders for the U.S. Demo Power Plant," Proc. 16th IEEE/NPSS Symp. Fusion Engineering, Champaign, Illinois, September 30-October 5, 1995, p. 1198, Institute of Electrical and Electronics Engineers (1995).
    • (1995) Proc. 16th IEEE/NPSS Symp. Fusion Engineering , pp. 1198
    • El-Guebaly, L.A.1
  • 27
    • 38249025773 scopus 로고
    • Thermal effect of periodical bakeout on tritium inventory in first wall and permeation to coolant in reactor life
    • K. NAKAHARA, Y. SEKI, and S. KOBAYASHI, "Thermal Effect of Periodical Bakeout on Tritium Inventory in First Wall and Permeation to Coolant in Reactor Life," Fusion Eng. Des., 10, 385 (1989).
    • (1989) Fusion Eng. Des. , vol.10 , pp. 385
    • Nakahara, K.1    Seki, Y.2    Kobayashi, S.3
  • 28
    • 0003618343 scopus 로고
    • UCLA-PPG-1323, University of California, Los Angeles
    • F. NAJMABADI et al., "The ARIES-I Tokamak Reactor Study," UCLA-PPG-1323, Vol. II, University of California, Los Angeles (1991).
    • (1991) The ARIES-I Tokamak Reactor Study , vol.2
    • Najmabadi, F.1
  • 29
    • 0031372549 scopus 로고    scopus 로고
    • Overview of ARIES-RS neutronics and radiation shielding: Key issues and main conclusions
    • L. A. EL-GUEBALY and the ARIES TEAM, "Overview of ARIES-RS Neutronics and Radiation Shielding: Key Issues and Main Conclusions," Fusion Eng. Des., 38, 139 (1997).
    • (1997) Fusion Eng. Des. , vol.38 , pp. 139
    • El-Guebaly, L.A.1
  • 30
    • 0028336175 scopus 로고
    • HYLIFE-II: A molten-salt inertial fusion energy power plant design
    • R. W. MOIR et al., "HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design," Fusion Technol., 25, 5 (1994).
    • (1994) Fusion Technol. , vol.25 , pp. 5
    • Moir, R.W.1
  • 31
    • 38149145260 scopus 로고
    • Critical technical issues and evaluation and comparison studies for inertial fusion energy reactors
    • M. A. ABDOU et al., "Critical Technical Issues and Evaluation and Comparison Studies for Inertial Fusion Energy Reactors," Fusion Eng. Des., 23, 251 (1993).
    • (1993) Fusion Eng. Des. , vol.23 , pp. 251
    • Abdou, M.A.1
  • 32
    • 0031336502 scopus 로고    scopus 로고
    • Complexity and availability for fusion power plants: The potential advantages of inertial fusion energy
    • L. J. PERKINS, "Complexity and Availability for Fusion Power Plants: The Potential Advantages of Inertial Fusion Energy," J. Fusion Energy, 16/4, 307 (1997).
    • (1997) J. Fusion Energy , vol.16 , Issue.4 , pp. 307
    • Perkins, L.J.1
  • 33
    • 0031120863 scopus 로고    scopus 로고
    • Liquid first walls for magnetic fusion energy configurations
    • R. W. MOIR, "Liquid First Walls for Magnetic Fusion Energy Configurations," Nucl. Fusion, 37/4, 557 (1997).
    • (1997) Nucl. Fusion , vol.37 , Issue.4 , pp. 557
    • Moir, R.W.1
  • 34
    • 0029275349 scopus 로고
    • A volumetric neutron source for fusion nuclear technology testing and development
    • M. A. ABDOU, "A Volumetric Neutron Source for Fusion Nuclear Technology Testing and Development," Fusion Eng. Des., 27, 111 (1995).
    • (1995) Fusion Eng. Des. , vol.27 , pp. 111
    • Abdou, M.A.1
  • 35
    • 0031131340 scopus 로고    scopus 로고
    • An assessment of the prospects for economic D-T tokamak fusion
    • S. P. WALKER and M. G. HAINES, "An Assessment of the Prospects for Economic D-T Tokamak Fusion," Fusion Eng. Des., 36, 387 (1997).
    • (1997) Fusion Eng. Des. , vol.36 , pp. 387
    • Walker, S.P.1    Haines, M.G.2


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