Loss Of Coolant Research Articles

The Comparative Study of the Sodium Loss Reactivity Effect of Large Pu-U and Pu-Th Fast Reactors

Fast reactors having a 3,000 l core volume fueled with ceramic Pu-U and Pu-Th are compared with each other for their reactivity effects due to large-scale loss of coolant. Using one-dimensional multi-group calculation, the maximum volume fractions of fuel for both fast systems are determined on the assumption that total loss of sodium in the core should not result in positive reactivity effect. It is concluded that Pu-Th fast reactors can be charged with more than several volume percent of fuel above the limit applicable to Pu-U fast reactors.

Vapor Cycle Coolant Requirements for Nuclear Space Power Plants

This paper includes a discussion of choice of coolants in the design of nuclear space power plants. Among the specific problems discussed are loss of coolant through meteoroid penetration, compatibility between coolant and construction materials at high temperatures, probability of damage by meteoroids and fabrication problems associated with large, lightweight, hermetically sealed structures which must be packageable, assembled in space and launched into orbit.

The Inertia Transient in Reactor Draining

The inertia transient in a nonconservative mass and energy system is discussed. The problem of reactor or tank draining is analyzed. The results have applieation in the design of reactor control or rt;actor scramming systems which depend upon the drainage of moderator or reflector liquid and may be of use in the evaluation of reactor hazards resulting from the loss of coolant or other reactor liquid. (A.C.)