Tritium supply assessment for ITER and DEMOnstration power plant

Abstract The International Thermonuclear Experimental Reactor (ITER) and next generation DEMOnstration fusion reactor need amounts of tritium for test/initial startup and will consume kilograms tritium for operation per year. The available supply of tritium for fusion reactor is man-made sources. Now most of commercial tritium resource is extracted from moderator and coolant of CANada Deuterium Uranium (CANDU) type Heavy Water Reactor (HWR), in the Ontario Hydro Darlington facility of Canada and Wolsong facility of Korea. In this study, the tritium production rate in CANDU reactor was simulated and estimated. And other possible routes, including Accelerator Production of Tritium (APT), tritium production in Commercial Light Water Reactor (CLWR) and Accelerator Driven Subcritical system (ADS), were also evaluated in feasibility and economy. Based on the tritium requirement investigated according to ITER test schedule and startup inventory required for a FDS-II-scale DEMO calculated by TAS1.0, the assessment results showed that after ITER retired in 2038, the tritium inventory of CANDU reactor could not afford DEMO reactor startup without extra resource.

[1]  Soon-Hwan Son,et al.  Tritium production, recovery and application in Korea. , 2009, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

[2]  Mohamed A. Abdou,et al.  Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors , 1986 .

[3]  S. Zheng,et al.  Preliminary neutronics design of the dual-cooled lithium lead blanket for FDS-II , 2005 .

[4]  P. Lisowski The Accelerator Production of Tritium (APT) Project , 1997 .

[5]  Yican Wu,et al.  Conceptual design of the China fusion power plant FDS-II , 2008 .

[6]  C. Jang,et al.  Tritium inventory prediction in a CANDU plant , 1995 .

[7]  Qunying Huang,et al.  Analysis on tritium controlling of the dual-cooled lithium lead blanket for fusion power reactor FDS-II , 2009 .

[8]  Yican Wu,et al.  Design status and development strategy of China liquid lithium-lead blankets and related material technology , 2007 .

[9]  Robert Hiergesell SPECIAL ANALYSIS: EVALUATION OF THE PROPOSED DISPOSAL OF THE INITIAL TEF-TPBAR WASTE CONTAINER WITHIN THE E-AREA LOW- LEVEL WASTE FACILITY INTERMEDIATE LEVEL VAULT , 2004 .

[11]  Yican Wu,et al.  Conceptual design activities of FDS series fusion power plants in China , 2006 .

[12]  Yican Wu,et al.  Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER , 2007 .

[13]  Qunying Huang,et al.  Analysis on Initial Tritium Supply for Starting Up Fusion Power Reactor FDS-II , 2011 .

[14]  A. Antipenkov,et al.  The ITER tritium systems , 2007 .

[15]  P. W. Lisowski,et al.  The Accelerator Production of Tritium project , 1997, Proceedings of the 1997 Particle Accelerator Conference (Cat. No.97CH36167).

[16]  P. Gierszewski,et al.  Tritium supply for near-term fusion devices , 1989 .

[17]  Richard E Rowberg The Department of Energy's Tritium Production Program , 1997 .

[18]  J. Quelch,et al.  Fusion technology experience at Ontario Hydro's Darlington Tritium Removal Facility and heavy water upgraders , 1990 .