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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.
There are drawbacks however. The similarity between the test reactor and the final design would be somewhat limited. Thus far, the Category III core has not proven safe for the common launch accident scenarios. The two alternatives that have been examined are listed below. One possible design uses pins that are at the upper limits of category III definition (49%, 49kg 235U) to achieve the desired results. In this case, the size of the fuel pins would have to be reduced or the number of pins would have to be reduced.
For the accident scenarios, the extra thermal absorption of neutrons from the additional rhenium dominated the effects from the additional fissionable fuel. 1 Immersion in Water In this scenario the reactor is immersed in water, and the gas flow region is flooded. It is assumed that the radial reflectors are all removed by any splashdown into water. This scenario results in the moderation of the fast neutrons and normally the increase in cross section with decreased neutron energy would result in an increase in reactivity.