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Supercritical Carbon Dioxide Cycle Control Analysis

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Supercritical Carbon Dioxide Cycle Control Analysis ( supercritical-carbon-dioxide-cycle-control-analysis )

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2.2. Comparison with Compressor Test Data One of the objectives of the ANL work for FY 2008 was a comparison of the compressor performance subroutine predictions with experiment data obtained at the Sandia National Laboratories (SNL) S-CO2 compression which is currently in operation at Barber-Nichols Inc. However, due to various delays in fabrication of the compression loop, no experiment data has been provided to ANL in FY 2008. It is expected that the data will be available next fiscal year such that the model validation task can be started in FY 2009. 2.3. Adaptation of Plant Dynamics Code for Sodium-Cooled Fast Reactors Since the focus of the S-CO2 cycle work for FY 2008 has been on developing the cycle for SFRs, work on adapting the ANL Plant Dynamics Code to SFRs has been initiated. The code was initially developed for LFRs; last year, the S-CO2 cycle part of the code was decoupled from the reactor part [1]. The reference SFR design for this work is the Advanced Burner Test Reactor (ABTR) [3, 4, and 5]. The Advanced Burner Test Reactor (ABTR) is a 96 MWe (equivalent to 250 MWt) metallic-fueled pool-type Sodium-Cooled Fast Reactor (SFR) operating with core outlet and inlet temperatures of 510 and 355°C, respectively. The ABTR was developed at Argonne National Laboratory (ANL) as a first step in demonstrating technologies for the transmutation of transuranics recovered from Light Water Reactor (LWR) spent fuel, and hence, the benefits of fuel cycle closure to nuclear waste management. Additional ABTR objectives are to 1) incorporate and demonstrate innovative design concepts and features that may lead to significant improvements in cost, safety, efficiency, reliability, or other favorable characteristics that could promote public acceptance and future private sector investment in Advanced Recycling Reactors (ARRs); 2) to demonstrate improved technologies for safeguards and security; and 3) to support development of the U.S. infrastructure for design, fabrication, and construction, testing, and deployment of systems, structures, and components for the ARRs. The reactor and S-CO2 cycle ABTR flow diagram is shown in Figure 3. In order to adapt the Plant Dynamics Code to SFRs, some modifications had to be made to the steady state part of the code. Most of the code modifications are due to presence of the intermediate sodium loop with intermediate heat exchangers (IHXs). Another major difference of the reference ABTR design compared to the reference STAR LFR designs is forced circulation of primary and intermediate coolants instead of natural circulation of the primary liquid metal coolant. The steady state code modifications include: • Geometric parameters of the primary system and the intermediate loop, such as core dimensions, thermal difference between the core and IHX, and so on; • IHX design, performance calculations, and pressure drops; 20

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