Title :
Thermohydraulic Analysis of the Z-Pinch Power Plant Primary Cycle
Author :
Modesto, M.A. ; Morrow, C.W. ; Lindgren, E.R. ; Vigil, V.L.
Author_Institution :
Sandia Nat. Labs., Albuquerque, NM
Abstract :
In this paper, we investigate the thermohydraulic characteristics of the Z-pinch power plant (ZIFE) primary cycle. The generation of electric energy using a power cycle is possible only if a minimum operating temperature is achieved and maintained in the primary cycle. Many energy losses are associated with the operation of the primary cycle. These thermal and pressure losses have a direct impact on the development of the concentrated thermal energy source (CTES) temperature profile. It also affects the component performance and the net electric energy generation. The effect of some important thermal and pressure losses is evaluated and their impact on the CTES temperature profile is estimated. The energy losses are grouped and presented as a percent of the total energy input. The temperature profile is modeled using two different approaches. The results of these models are used to determine the time needed to reach steady state conditions. The major components of the primary cycle are: the CTES, the main heat exchanger (MHX), and the piping system. Lithium is a required component of the liquid wall for breeding the tritium fuel required to sustain the process. In this study Flibe is selected to serve as the heat transport media. Flibe is a 2:1 mixture of the salts lithium fluoride (LiF) and beryllium fluoride (BeF2). Thermohydraulic analyses were performed for each component. The outcome of the two models can be used as two limiting cases to establish the correct time to start the energy generation. These preliminary results serve as the basis for future research toward the development of a general thermohydraulic model of the ZIFE power plant
Keywords :
Z pinch; fusion reactor fuel; fusion reactor operation; heat exchangers; heat transfer; nuclear power stations; CTES temperature profile; Flibe; Li2BeF4; LiF; MHX; Z-pinch power plant primary cycle; ZIFE power plant; beryllium fluoride; component performance; concentrated thermal energy source; energy loss; heat transport media; liquid wall; lithium; lithium fluoride salt; main heat exchanger; minimum operating temperature; net electric energy generation; piping system; power cycle; pressure loss; steady state conditions; thermal loss; thermohydraulic analysis; total energy input; tritium fuel; Energy loss; Fuels; Fusion power generation; Laboratories; Lithium; Nuclear power generation; Power generation; Power generation economics; Steady-state; Temperature;
Conference_Titel :
Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
Conference_Location :
Knoxville, TN
Print_ISBN :
0-4244-0150-X
Electronic_ISBN :
0-4244-0150-X
DOI :
10.1109/FUSION.2005.252959