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GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO2

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GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO2 ( gas-cooled-fast-reactor-with-indirect-supercritical-co2 )

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ASSESSMENT OF GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO2 CYCLE P. HEJZLAR1*, V. DOSTAL2, M.J. DRISCOLL1, P. DUMAZ3, G. POULLENNEC3 and N. ALPY3 1 Massachusetts Institute of Technology, 77 Massachusetts Ave., Cambridge, MA, 02139 2 Presently at Czech Technical University, Technicka 4, 16607 Prague, Czech Republic 3 CEA-Cadarache, DER, 13108 Saint-Paul lez Durance, France *Corresponding author. E-mail : Hejzlar@mit.edu Received January 19, 2006 Various indirect power cycle options for a helium cooled gas cooled fast reactor (GFR) with particular focus on a supercritical CO2 (SCO2) indirect cycle are investigated as an alternative to a helium cooled direct cycle GFR. The balance of plant (BOP) options include helium-nitrogen Brayton cycle, supercritical water Rankine cycle, and SCO2 recompression Brayton power cycle in three versions: (1) basic design with turbine inlet temperature of 550°C, (2) advanced design with turbine inlet temperature of 650°C and (3) advanced design with the same turbine inlet temperature and reduced compressor inlet temperature. The indirect SCO2 recompression cycle is found attractive since in addition to easier BOP maintenance it allows significant reduction of core outlet temperature, making design of the primary system easier while achieving very attractive efficiencies comparable to or slightly lower than, the efficiency of the reference GFR direct cycle design. In addition, the indirect cycle arrangement allows significant reduction of the GFR “proximate-containment” and the BOP for the SCO2 cycle is very compact. Both these factors will lead to reduced capital cost. KEYWORDS : Supercritical Carbon Dioxide, Indirect Power Cycle, Gas Cooled Fast Reactor 1. INTRODUCTION The gas cooled fast reactor (GFR) with helium Brayton direct cycle is the reference design under consideration for Generation IV service because of its simplicity, high achievable efficiency and synergism with its thermal counterpart, as a very high temperature reactor for electricity generation and hydrogen production. On the other hand, GFR fuel requires much higher heavy metal loading than the particle fuel for thermal gas cooled reactors and thus gives less freedom in the application of several layers of coatings, which provide effective barriers to fission product release. The development of a robust fuel that meets extremely stringent integrity and leak tightness requirements at high operating temperatures will be challenging, especially for the direct cycle where minimum or no contamination of turbomachinery is desirable. Therefore, investigation of an indirect cycle as a backup to the reference direct cycle design is of high interest. The indirect cycle also provides benefits of reduced containment cost (because the power cycle can be located outside the containment), easier mai- ntenance of turbomachinery, reduction of LOCA initiators, and the possibility to use reheat, which is not practical for a direct cycle. This paper summarizes results of studies on the performance of a helium-cooled GFR coupled to a supercritical CO2 (SCO2) cycle carried out at MIT and CEA within the framework of the International Nuclear Energy Research Initiative (I-NERI). The reason for selecting a supercritical cycle for the balance of plant (BOP) is the potential for high efficiency at significantly lower temperature than for the Brayton helium cycle due to low compression work near the critical point. Among several different fluids, CO2 was selected as the most promising candidate because of the moderate value of the critical pressure, its stability, relative inertness (for the temperature range of interest), sufficient knowledge of the thermodynamic properties, non-toxicity, low cost and abundance. A supercritical CO2 cycle was first proposed in 1948 when Sulzer Bros patented a partial condensation CO2 Brayton cycle [1]. More extensive studies of supercritical CO2 cycles were carried out in the sixties by several inve- stigators. In the U.S. Feher [2] proposed a cycle which operated entirely above the critical pressure of carbon dioxide with the compression process in the liquid phase below the critical temperature (critical point 7.377 MPa, 30.97°C) to minimize pump work. Angelino performed an extensive review of various arrangements of SCO2 NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.38 NO.2 SPECIAL ISSUE ON ICAPP ‘05 109

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