THE METHODOLOGY OF THE EXPERIMENTS ON TRITIUM GENERATION AND RELEASE FROM THE Li15.7Pb LEAD LITHIUM EUTECTIC UNDER REACTOR IRRADIATION

In this paper, the methodology of the experiments on tritium generation and release from the Li15.7Pb lead-lithium eutectic under neutron irradiation is presented. Using the MCNP software, the neutron-physical calculations were performed. As a result of calculations, the power of energy release from the sample and from the design elements of ampoule device at the level of 1 MW thermal power are determined. Using the ANSYS software packages, thermophysical calculations for different temperature modes of eutectic at 1–6 MW stationary reactor power levels has been carried out. Based on the calculations a special irradiation ampoule device (AD) was developed. The cleaning and filling of the lead-lithium eutectic into AD were conducted. The methodical experiments to determine the irradiation parameters of eutectics and to determine the mass-spectrometric registration modes of tritium in ampoule device was performed. The preliminary results of the methodical experiments were presented.

1. A. Li-Puma, J. Bonnemason, L. Cachon, J.L. Duchateau, F. Gabriel. Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor // Fusion Engineering and Design 84, 2009. P. 1197–1205.

2. Malang S. et al. An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dualcoolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step // Fusion Engineering and Design, 2009. V. 84. P. 2145–2157.

3. Di Maio P.A. et al. Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions // Fusion Eng. Des. 2015. In press. (http://dx.doi.org/10.1016.j.fusengdes.2015.03.051).

4. Sawan M.E. et al. Three-dimensional nuclear analysis for the US dual coolant lead lithium ITER test blanket module // Fusion Engineering and Design, 2010. V. 85. P. 1027–1032.

5. Sadhana Mohan, Kalyan Bhanja, K.C. Sandeep. Experimental design of tritium extraction loop from lead lithium eutectic // Fusion Engineering and Design, 85, 2010, P. 803–808.

6. V. Kapyshev, I. Danilov, I. Kartashev, V. Kovalenko, A. Leshukov, V. Poliksha, A. Razmerov, Yu. Strebkov, M. Sviridenko, E. Trusova, N. Vladimirova, A. Kalashnikov. Initial design and test of the tritium breeder monitoring system for the lead-lithium cooled ceramic breeder (LLCB) module of the ITER // Fusion Engineering and Design, 88, 2013, P. 2293–2297.

7. Yong Song, Qunying Huang, Yongliang Wang, Muyi Ni. Analysis on tritium controlling of the dual-cooled lithium lead blanket for fusion power reactor FDS-II // Fusion Engineering and Design, 84, 2009, P. 1779–1783.

8. Irina Tazhibayeva, Timur Kulsartov, Nikolay Barsukov, Yuri Gordienko, Yuri Ponkratov, Zhanna Zaurbekova, Eugeniy Tulubayev, Vyachaslav Gnyrya, Viktor Baklanov, Ergazy Kenzhin. Interaction of tritium and helium with lead–lithium eutectic under reactor irradiation // Fusion Engineering and Design, 89, 2014, P. 1486–1490.

9. Takayuki Terai and Satoru Tanaka. Tritium release behavior from liquid tritium breeding materials for fusion reactor blanket under neutron irradiation. Progress in Nuclear Energy, Vol 32, No. 1/2, 1998. P. 97–112.

10. A. Li Puma, J.L. Berton, B. Branas, L. Bühler, J. Doncel. Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant // Fusion Engineering and Design, 81, 2006, P. 469–476.

11. S. Fukada, T. Terai, S. Konishi, K. Katayama, T. Chikada, Y. Edao, T. Muroga, M. Shimada, B. Merrill and D. K. Sze. Clarification of Tritium Behavior in Pb¬Li Blanket System // Materials Transactions, Vol. 54, No. 4, 2013, P. 425–429.

12. Субботин B.H., Арнольдов M.H., Ивановский M.H., Мосин А.А., Тарбов А.А. Литий. М.: Атом, 1999. 263 с.