Abstract: The present invention relates generally to both a system and method for determining the composition of an off-gas from a solution nuclear reactor (e.g., an Aqueous Homogeneous Reactor (AHR)) and the composition of the fissioning solution from those measurements. In one embodiment, the present invention utilizes at least one quadrupole mass spectrometer (QMS) in a system and/or method designed to determine at least one or more of: (i) the rate of production of at least one gas and/or gas species from a nuclear reactor; (ii) the effect on pH by one or more nitrogen species; (iii) the rate of production of one or more fission gases; and/or (iv) the effect on pH of at least one gas and/or gas species other than one or more nitrogen species from a nuclear reactor.

Abstract: A hybrid arrangement allows an existing circuit switched telephony network to be deployed on a packet switched network. The circuit switched underlying transport network is replaced with that of an IP based package switched network, while the circuit switched infrastructure, such as terminals, telephone exchanges and the like are retained. Both a subscriber and a local telephone exchange are connected to, and separated by, an IP based packet switched network, such as the Internet. Signalling between the subscriber and exchange are effected using a standard user to network protocol, such as V5.1 for PSTN and ISDN BRI or DSS1 for ISDN PRI. This standard user network is overlaid on an IP based network protocol, such as TCP or UDP on IP.

Abstract: A Critical Channel Power (CCP) enhancement system is provided for a pressurized fuel-channel-type water-cooled nuclear reactor of the type adapted to be refuelled on-line by the insertion and removal of fuel bundles onto and from of a plurality of said fuel channel assemblies, each of said fuel channel assemblies. A means is provided for interlocking fuel bundles into pairs having their fuel elements aligned, thereby lowering the hydraulic resistance in the fuel channel and enhancing CCP. The means for interlocking prevents misalignment of the paired bundles during their residence time inside the reactor due to continuous rocking and vibration of the fuel bundles exposed to very high coolant mass flow rate and misalignment due to axial separation of bundles impacting upon one another during fuelling operations.

Abstract: The present invention relates to a miniaturized nuclear utilizing improved pressure tube structural members. More particularly, the present invention relates to a new miniaturized nuclear reactor utilizing novel structural members that are used to support the loads and stresses of multiple nuclear reactor fuel channel pressure tubes and calandria tubes in a moderator.

Abstract: A critical power enhancement system is provided for a pressurized fuel channel type nuclear reactor comprising a plurality of fuel bundles contained in a fuel channel and containing a plurality of fuel elements horizontally oriented within the fuel channel. The system comprises at least one appendage strategically located on each of certain fuel elements along its length and projecting outwardly from the surface of the fuel element. The appendages generate turbulence in the coolant flowing at locations along the length of the fuel bundle, where the critical heat flux is most likely to occur. The presence of the appendages suppress the occurrence of the critical heat flux in the fuel bundle thereby increasing the safety limit on the maximum power that can be produced by the reactor.

Abstract: To preclude failure of components of control-rod assemblies or of unprotected control rods (WDRC's) a calandria is provided above the upper internals. The calandria includes hollow tubes through which the drive rods for the various control rods pass and which protect the drive rods. The guides for the control rods are closed except at the top so that the coolant flows vertically through the guides into the calandria. In the calandria, the coolant flows transversely to the hollow tubes and out through the outlet nozzle. The tubes have a mass and stiffness and strength such that they resist failure by reason of the transverse flow of the coolant to which they are subjected.