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May 2009
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82 Reads
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6 Citations
Poster Presentation given at the ANS-sponsored Mathematics and Computations (M&C) 2009 Conference held on May 4, 2009 at Saratoga Springs, NY. Poster on the Comparison of MCNP and WIMS-AECL/RFSP Calculations Against Critical Heavy Water Experiments in the ZED-2 Critical Facility using Mixed Lattices of CANFLEX-LVRF and CANFLEX-LEU Test Fuels
May 2009
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17 Reads
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5 Citations
This paper summarizes calculations of MCNP5 and WIMS-AECL/RFSP compared against measurements in coolant void substitution experiments in the ZED-2 critical facility with CANFLEX-LEU/RU (Low Enriched Uranium, Recovered Uranium) reference fuels and CANFLEX-LVRF (Low Void Reactivity Fuel) test fuel, and H2O/air coolants. Both codes are tested for the prediction of the change in reactivity with complete voiding of all fuel channels, and that for a checkerboard voiding pattern. Understanding these phenomena is important for the ACR-1000 reactor. Comparisons are also made for the prediction of the axial and radial neutron flux distributions, as measured by copper foil activation. The experimental data for these comparisons were obtained from critical mixed lattice / substitution experiments in AECL's ZED-2 critical facility using CANFLEX-LEU/RU and CANFLEX-LVRF fuel in a 24-cm square lattice pitch at 25 C. Substitution analyses were performed to isolate the properties (buckling, bare critical lattice dimensions) of the CANFLEX-LVRF fuel. This data was then used to further test the lattice physics codes. These comparisons establish biases/uncertainties and errors in the calculation of keff, coolant void reactivity, checkerboard coolant void reactivity, and flux distributions. Results show small to modest biases in void reactivity and very good agreement for flux distributions. The importance of boundary conditions and the modeling of unmoderated fuel in the critical experiments are demonstrated. This comparison study provides data that supports code validation and gives good confidence in the reactor physics tools used in the design and safety analysis of the ACR-1000 reactor.
... The core and fuel bundle / lattice (see also Section IV.A) specifications are shown in Table I and related details can be found in earlier publications [7][8][9][10][11][12][13] . The lattice was selected on the basis of a range of lattice physics scoping studies, with the objectives of achieving burnups 20 MWd/kg, and also reducing the coolant void reactivity (CVR) to lower levels ( +11 mk), (1 mk = 100 pcm = 0.001 k/k) than what may be found using NU bundles in PT-HWRs 6,7,14 . ...
May 2009
... The B37-mod concept uses either recovered uranium (RU, ~0.95 wt% U-235/U) or slightly enriched uranium (SEU, ~1.2 wt% U-235/U) instead of natural uranium, permitting higher burnups (11 MWd/kg to 18 MWd/kg). In the BUNDLE-35 (B35) concept, which is similar to the 43-element CANFLEX fuel bundle concept [12], the two inner rings of fuel pins are replaced by a central graphite displacer rod, which also helps to reduce CVR. The two outer concentric rings of 35 (14+21) fuel pins are made of a variety of advanced thorium-based fuels, including (Pu,Th)O2, (LEU,Th)O2, and (U-233,Th)O2, as discussed in previous studies( [6] to [11]), and as shown in Table I. ...
May 2009
