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2% offset yield strength was 245 MPa at 860 K. In all likelihood, all three limits are close to the same value at the expected operation temperature. 8%, as shown in Figure 3-7. 5 Beryllium Oxide BeO is a ceramic with a 1-to-1 atom ratio of beryllium to oxygen. It is primarily used in the nuclear field as a neutron reflector. The oxygen component results in BeO being an extremely good scattering material as it has a very high scattering to absorption cross section ratio. In addition to being a reflector, there is an n-2n reaction in beryllium that increases neutron numbers, increasing this material’s attractiveness.

Additionally, a study to determine the effect of the Nb1Zr cladding on the neutronics of the system. 1 Initial Calculations This section will cover some simple calculations related to the reactor. 0065. The burnup for the reactor was determined using a fairly simple set of equations. 6 kgs of 235U would be consumed. 86% for the upper end of the uranium consumed. This burnup results in a loss of $1 reactivity. 2 Reactor Multiplication Vs Reflector Position The primary goal of this study was to ensure that there was sufficient excess reactivity in the neutron multiplication factor to keep the reactor critical for the 10 year lifespan while ensuring that the reactor would be subcritical during major accident scenarios.

43 This ensures that while the volumes of components in the core are changing, the mass of each material remains constant. Finally, the cross sections of the materials being used in the core were corrected to those at operating temperature The vast majority of the materials in the core do not have readily available cross sections at the desired temperature. The NJoy code was used to generate cross sections for the different materials in the reactor [MacFarlane, 1994]. The temperatures used were the peak values from the FEPSIM model.

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