The pressurizer system and its related design and operating data are described. The philosophy and analytical procedures used in the design of the pressurizer for the Consolidated Edison Thorium Reactor are summarized

Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem

A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high temperature.

Although there have been several previous investigations of neutron resonance absorption in thorium, knowledge in this area has not been sufficiently accurate nor extensive enough to satisfy the practical requirements of thorium breeder reactor design. The present experiment was performed in an effort to reduce this uncertainty by checking and extending the results of previous measurements of the geometric and temperature dependence of thorium resonance integrals. The experimental procedure was the determination of reactivity coefficients by measurements of reactor period in the Lynchburg Pool Reactor.