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4. Publications A paper entitled “Controllability of the Supercritical Carbon Dioxide Brayton Cycle Near the Critical Point” by A. Moisseytsev and J. J. Sienicki was presented at the 2008 International Congress on Advances in Nuclear Power Plants (ICAPP ‘08) in Anaheim, CA, June 8-12, 2008. The paper summarizes the work on S-CO2 cycle development performed at ANL during the last fiscal year. A. Moisseytsev and J. Sienicki attended the ICAPP ‘08 conference to present the paper and participate in the Innovative/Advanced Energy Conversion System session of the conference as well as in other discussions related to S-CO2 cycle at the conference. A paper entitled “Transient Accident Analysis of a Supercritical Carbon Dioxide Brayton Cycle Energy Converter Coupled to an Autonomous Lead-Cooled Fast Reactor” by A. Moisseytsev and J. J. Sienicki has been published in the journal, Nuclear Engineering and Design, No.238 (2008), pp. 2094-2105. 5. Summary and Conclusions The ANL Plant Dynamics Code has been applied to investigate the dynamic behavior of the 96 MWe (250 MWt) Advanced Burner Test Reactor (ABTR) S-CO2 Brayton cycle power converter preconceptual design following a design basis event reactor scram. The timescale for the primary sodium flowrate to coast down and for the transition to natural circulation of the primary sodium coolant to occur was calculated with the SAS4A/SASSYS-1 computer code and found to be about 400 seconds. The ANL Plant Dynamics Code configured for the Small Secure Transportable Autonomous Reactor (SSTAR) Lead-Cooled Fast Reactor (LFR) was utilized to approximately model the ABTR S-CO2 Brayton cycle power converter with a decaying liquid metal coolant flow to the Pb-to-CO2 heat exchangers and temperatures reflecting the decaying core power and heat removal by the cycle. The Plant Dynamics Code calculations show that the S-CO2 cycle continues to operate for about 400 seconds following reactor scram driven by the thermal energy stored in the reactor structures and coolant such that heat removal from the reactor exceeds the decay heat generation in the core. Following this time, decay heat will be removed by the normal ABTR shutdown heat removal system incorporating a dedicated shutdown heat removal S-CO2 pump and cooler. Thus, the S- CO2 Brayton cycle power converter is calculated to remove greater heat from the reactor system than is generated by the decay heat in the core until the normal shutdown heat removal system is placed into operation which is assumed to happen by 400 seconds following scram. Based on the calculations, requirements for the shutdown heat removal system have been defined including the capability to remove 1.1 % of the nominal reactor power. If the normal shutdown heat removal system were postulated to be unavailable after 400 seconds, then the Direct Reactor Auxiliary Cooling System (DRACS) heat exchangers immersed in the primary sodium pool for emergency decay heat removal would subsequently remove the core heat generation. 40PDF Image | Supercritical Carbon Dioxide Cycle Control Analysis
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