By G T Mays; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information
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Postirradiation examination of the graphite foam samples discussed in Sect. 1 included dimensional changes, microstructural examination, and thermal conductivity. Here we discuss the effect of neutron irradiation on the dimensions of the graphite foam samples. , the average number of times each carbon atom is displaced from its equilibrium lattice position). The volume change was determined from the pre- and postirradiation specimen dimensions. As indicated by the data in Fig. 21, the volume change behavior is dominated by a rapid swelling of the graphite foam at relatively low doses, followed by a turnaround to shrinkage.
This criterion results in the number of control rods being 18. 9 Consequence of Water Ingress Accident During the operation of the Fort St. Vrain gas-cooled reactor, an incident occurred in which a large quantity of water leaked from a water-cooled bearing to a coolant loop and ultimately to the reactor core. While it is not certain that the SSR would employ a similar circulation system, the possibility of a transportation accident leading to water immersion of the SSR or the possibility of water vapor ingress to the core coolant are safety-related scenarios that should be considered in the design of the reactor.
5 mm is the same for vessels of both wall thicknesses. 3 cm. 6 cm from the reflector top (Fig. 7). 0 C97 0480 Fig. 7. Longitudinal section of the critical assembly with structural elements of the facility (dimensions given in cm). 0 C97 0481 Fig. 8. Cross section of the critical assembly showing the arrangement of channels (dimensions given in cm). 5 Fig. 9. Longitudinal section of the assembly core (dimensions given in cm). The core vessel was surrounded with a graphite reflector. In its external shape, the graphite reflector with the shield is represented by a rectangular parallelepiped.
Solid State Reactor Final Report by G T Mays; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information
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