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CHAetal., DevelopmentofaSupercriticalCO2BraytonEnergyConversionSystemCoupledwithaSodiumCooledFastReactor Fig. 14. Total Heat Transfer Rate and Pressure Drop in the Cold Channels of the Zigzag Channel PCHE and Airfoil Fin PCHEs The new design concept was also evaluated by three- dimensional numerical analyses, which have showed that the airfoil shape fin heat exchangers conserve the total heat transfer rate and reduce the pressure drop to 1/14. The structural robustness of the PCHE has been evaluated by mechanical and stress analysis tools and its thermal and hydraulic performance is also under investigation by experimental tests. 4. TRANSIENTANALYSIS 4.1 System Transient Analysis with the MMS-LMR In order to simulate the system transient and evaluate control logics, the KALIMER-600 S-CO2 Brayton cycle was modeled based on the MMS-LMR code. The basic modules in the MMS code have been developed for water and general gas plants like PWRs [24]. The property tables as well as the heat transfer models for sodium and supercritical CO2 have been developed and implemented in the MMS code through user FORTRAN routines; this is called the MMS-LMR code. Based on the MMS-LMR modules, we have developed the KALIMER-600 loop model for analyzing a sodium- cooled fast reactor, the KALIMER-600. The model is composed of a reactor module, various pipe modules, and an IHX, as well as Na-CO2 HX, and HTR and LTR heat exchangers. The developed model is shown in Figure 15. For a simple analogy, we have modeled each loop (PHTS, IHTS, and Brayton cycle) as a single loop. The model is composed of a core module, a loop module with various pipe modules including a pump module, an IHX, and various PCHE heat exchangers. Since a gas turbine for the S-CO2 Brayton cycle has not yet been sufficiently developed, we assumed the turbine/generator as a heat sink in this model. The Na loop and the CO2 cycle are modeled separately and, finally, linked to the PHTS/IHTS model. Additionally, the cooler in the S-CO2 Brayton cycle was assumed to be an ideal cooler. This means the cooler’s outlet condition is always the same (7.4MPa and 31.25 oC). The core module was developed from a point kinetics equation for a nuclear core. The kinetic parameters are the prompt neutron generation time, the delayed neutron fraction, the poisoning effect from poison materials like Xeon and Iodine, and the reactivity coefficients from the sodium density change and the Doppler phenomena. In a fast reactor, the reactivity effect from the poisoning materials can be negligible due to the fast neutron spectrum. The coefficient for the sodium density is represented by the change of reactivity due to the change of sodium density in the core region. We represented all the heat exchangers like the IHX, the Na-CO2 HX, the HTR and the LTR HXs by using a pipehx module, a qmetal module, and another pipehx module in the MMS-LMR code. The pipehx module can simulate the heat transfer from a metal surface of a heat exchanger; the qmetal module can analyze the heat transfer in a metal. Each component and pipe data were retrieved from the heat balance of the KALIMER-600. Table 12 shows the analysis results for the steady state of the full 1038 NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.41 NO.8 OCTOBER 2009PDF Image | DEVELOPMENT OF A SUPERCRITICAL CO2 BRAYTON ENERGY CONVERSION
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