Chemistry Inorganic, Organic, Physical And Analytical Chemistry

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

Authors: G. S. Chang M. A. Lillo
 
Abstract: 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°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.
Publication Date: 01 May 2008
Report numbers: INL/CON-07-13152
DOE Contract number: DE-AC07-99ID-13727
Resource Type: Conference
Resource Relation: Conference: 13th International Symposium on Reactor Dosimetry,Petten, The Netherlands,05/25/2008,05/30/2008
Research Organizations: Idaho National Laboratory (INL)
Sponsoring Organizations: DOE - NE
Country of Publication: United States
Language: English

Subjects:
Related subjects:
GAS TEST LOOP EXPERIMENT
MCNP
SILICIDE DISPERSION FUEL