Abstract: Piping loops can carry either forced or natural circulation coolant flow from and back to a nuclear reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing isolation condenser systems or come off of a primary loop generating electricity commercially. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.

Abstract: Systems reduce noncondensable gasses within coolant systems with a recombiner into which the fluid coolant flows. Flow through the recombiner may be opposite that of a heat exchanger. The recombiner includes a catalyst that combines or degrades the noncondensable gasses, such as a Group 9-11 transition metal that speeds reaction of noncondensable gasses. The catalyst may be a liner, plate, aggregate, et. with openings through which all coolant must flow. The recombiner may be insulated to prevent heat exchange and condensation and may be tilted from a vertical to enhance draining and fluid flow. The entire system may be passive without any operator intervention or moving structures. Systems can be made from isolation condenser systems in nuclear power plants in an isolation condenser pool by adding a recombiner to existing coolant systems. Systems may also be made by including a recombiner with new isolation condensers.

Abstract: Piping loops can carry either forced or natural circulation coolant flow from and back to a reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that significantly cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing ICSs, come off of a primary loop generating electricity commercially, or be their own loop around and penetrations to the reactor. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.

Abstract: Nuclear fuel assembly support castings direct fluid flow through nuclear fuel assemblies with relatively lower decay ratios and thus improved flow stability. The castings include an internal flow passage that is elongated to increase fluid flow inertia. The passage may be in excess of 0.3 meters and up to several meters in a straight, vertical direction that does not disrupt inertial fluid flow. Castings may omit an entry orifice and replicate any orifice-driven pressure drop with a specifically-sized flow passage that causes a similar pressure drop, or castings may use a side or bottom entry orifice at an entrance to the passage. Castings accommodate any number of fuel assemblies and other core structures including control blades, instrumentation tubes, core plates, and other core structures, such as four fuel assemblies arranged in a grid on the casting with a cruciform control element extending through a center of the casting.

Abstract: In one embodiment, the heat removal system includes a storage tank configured to store a heat transfer medium, a transfer system configured to selectively transfer the heat transfer medium from the storage tank to the nuclear reactor, and a delivery system operationally connected to the transfer system. The delivery system is configured to deliver the heat transfer medium to a suppression pool room of the nuclear reactor. The suppression pool room houses a suppression pool.

Abstract: A method and system for thermal-dynamic modeling and performance evaluation of a nuclear Boiling Water Reactor (BWR) core design is presented. A data processing system is used to execute specific program routines that simultaneously simulate the thermal operating characteristics of fuel rods (or plural groups of fuel rods) within the reactor during a transient operational condition. The data processing system is also used for compilation of a transient response histogram that incorporates the effect of inherent "uncertainties" in various parameters of interest. In an initial phase, the method employs a multi-dimensional approach for the simulation of postulated operational events or an anticipated operational occurrence (AOO) which produces a transient condition in the reactor--such as might be caused by single operator error or equipment malfunction.