详情

原文传递 Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position

题名：	Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position
作者：	M. A. Lillo;G. S. Chang;
关键词：	gas test loop experiment; MCNP; silicide dispersion fuel11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BURNUP; DESIGN; DOSIMETRY; ENRICHED URANIUM; FISSION; FUEL PLATES; HEAT FLUX; IRRADIATION; NEUTRONS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SECURITY; SELF-SHIELDING; SPENT FUELS; TEMPERATURE DISTRIBUTION; TESTING; THICKNESS; URANIUM
摘要：	The NNSA (National Nuclear Security Administration) RERTR (Reduced Enrichment for Research and Test Reactors) program assigned INL (Idaho National Laboratory) the responsibility of developing and demonstrating high uranium density research reactor fuel forms to enable the use of low enriched uranium (LEU) in the research reactors around the world. A series of full-size fuel plate irradiation tests are proposed for the ATR (Advanced Test Reactor). Labeled the AFIP (ATR Full-size-plates In center flux trap Position) experiments, these tests will be conducted in the ATR center flux trap. The AFIP-2 experiment will contain two full size fuel plates fabricated at the Oak Ridge National Laboratory-Y-12 (ORNL). The nominal fuel zone is rectangular in shape having a designed length of 21.5-in (54.6l-cm), width of 1.6-in (4.064-cm), and uniform thickness of 0.014-in (0.03556-cm). This gives a nominal fuel zone volume of 0.482 in3 (7.89 cm3) in each fuel plate. The test holder accommodates two independent test trains. Each test train is designed to hold 2 plates, for a total of 4 plates per test holder. AFIP-2 test plates will be irradiated at a peak surface heat flux of about 350 W/cm2 and discharged at a peak U-235 burn-up of about 70 at.%. Based on limited irradiation testing of the monolithic (U10Mo) fuel form, it is desirable to keep the peak fuel temperature below 250掳C; to achieve this, it will be necessary to keep plate heat fluxes below 500 W/cm2. Due to the heavy U-235 loading and width of 1.6-in (4.064 cm), the neutron self-shielding will increase the local-to-average-ratio fission power near the sides of the fuel plates. To assure the AFIP-2 experiment will comply with the ATR safety requirements, a very detailed 2 dimensional (2D) Y-Z fission power profile was evaluated to best predict the fuel plate temperature distribution. The ability to accurately predict fuel plate power and burnup are essential in the AFIP-2 fuel test train design and the irradiated fuel performance evaluation. We obtained the required power and heat generation rates within test train for the thermal analyses. A detailed MCNP Y-Z mini-plate fuel model was developed. The Y-Z model divides each fuel mini-plate into 30 equal intervals in Y and Z directions. The MCNP-calculated results and the detailed Y-Z fission power mapping were used to help design the AFIP-2 fuel test assembly to ensure that the capsule thermal-hydraulic limits will not exceed the ATR safety limit.<
报告类型：	科技报告