Abstract: The disclosed apparatus includes a condensing chamber (CC) that maintains a volume of a condensate obtained from vapor emitting from a vessel, for example a reactor pressure vessel (RPV). The condensing chamber is connected to a reference leg (RL), a variable leg (VL) and a vapor or steam leg (SL). RL connection provides a flow path for the CRD drive water system backfill to flow into the CC and overflow into the VL. The excess backfill and/or condensate will be returned to the vessel, typically at a point below the liquid level within the vessel. Non-condensable gases will thereby be returned from the CC to the RPV in a substantially continuous manner, thereby tending to prevent the introduction of non-condensable gas enriched liquid from the CC into the RL and improving the tolerance and reliability of the level measurements and/or reducing thermal stresses on the various CC connections.

Abstract: The disclosed apparatus includes a condensing chamber (CC) that maintains a volume of a condensate obtained from vapor emitting from a vessel, for example a reactor pressure vessel (RPV). The condensing chamber is connected to a reference leg (RL), a variable leg (VL) and a vapor or steam leg (SL). RL connection provides a flow path for the CRD drive water system backfill to flow into the CC and overflow into the VL. The excess backfill and/or condensate will be returned to the vessel, typically at a point below the liquid level within the vessel. Non-condensable gases will thereby be returned from the CC to the RPV in a substantially continuous manner, thereby tending to prevent the introduction of non-condensable gas enriched liquid from the CC into the RL and improving the tolerance and reliability of the level measurements and/or reducing thermal stresses on the various CC connections.

Abstract: A method for calculating a fatigue usage factor of a component in a nuclear reactor includes determining a flow scaling factor for each stress component of a stress cycle, applying the flow scaling factor to rapid cycling stress conditions, and performing a fatique evaluation by calculating a fatigue usage factor using the flow scaling factor. The flow scaling factor is a ratio of a temperature fluctuation ratio at a first reactor operating condition divided by a temperature fluctuation ratio at a second reactor operating condition. The temperature fluctuation ratio is defined as a ratio of the metal temperature range over the fluid temperature range.

Abstract: A nuclear reactor core is provided that includes a plurality of fuel assemblies. In an exemplary embodiment, each fuel assembly includes a main coolant flow channel having an inlet. The plurality of fuel assemblies are arranged into at least three regions within the core. The flow channels are configured so that the flow of coolant through the main coolant flow channels of the fuel assemblies located in a particular region are substantially the same, and that the coolant flow through the fuel assemblies in each region is different from the coolant flow through the fuel assemblies in each other region.

Abstract: A method for calculating a fatigue usage factor of a component in a nuclear reactor includes determining a flow scaling factor for each stress component of a stress cycle, applying the flow scaling factor to rapid cycling stress conditions, and performing a fatigue evaluation by calculating a fatigue usage factor using the flow scaling factor. The flow scaling factor is a ratio of a temperature fluctuation ratio at a first reactor operating condition divided by a temperature fluctuation ratio at a second reactor operating condition. The temperature fluctuation ratio is defined as a ratio of the metal temperature range over the fluid temperature range.

Abstract: A reactor pressure vessel (RPV) for a nuclear reactor that permits measurement of the flow through each reactor internal pump (RIP) is described. The reactor pressure vessel also includes at least one reactor internal pump that includes an impeller and a pump diffuser. At least two seal rings extend circumferentially around an outer surface of the diffuser housing outer wall and are located in circumferential grooves in the housing outer wall. At least one lateral bore extends through the housing outer wall into a diffuser housing longitudinal flow passage. Each lateral bore is located in an area between two adjacent seal rings, with each inter-seal ring area containing one lateral bore. At least one pressure tap bore extends from the outer surface of the RPV bottom head petal, through the pump deck to an inner surface of a pump deck opening. Each pressure tap bore is aligned with an area in the RIP containing a corresponding lateral bore.

Abstract: Terminally-branched polymeric prodrug platforms capable of high degrees of loading are disclosed. In preferred aspects of the invention, the prodrug platform releases multiple parent compounds after each branch holding the active agent undergoes a benzyl elimination reaction. Methods of preparing the prodrugs and using the same in the treatment of mammals are also disclosed.

Abstract: Terminally-branched polymeric prodrug platforms capable of high degrees of loading are disclosed. In preferred aspects of the invention, the prodrug platform releases multiple parent compounds after each branch holding the active agent undergoes a benzyl elimination reaction. Methods of preparing the prodrugs and using the same in the treatment of mammals are also disclosed.

Abstract: The present invention is directed to polymeric-prodrug transport forms of the formula: wherein: G is a linear or branched, terminally functionalized polymer residue; Y1 is O, S, or NR1; M is X or Q; wherein X is an electron withdrawing group and Q is a moiety containing a free electron pair positioned three to six atoms from C(═Y1); R1-5 are independently selected from the group consisting of hydrogen, C1-6 alkyls, C3-12 branched alkyls, C3-8 cycloalkyls, C1-6 substituted alkyls, C3-8 substituted cycloalkyls, aryls, substituted aryls, aralkyls, C1-6 heteroalkyls, substituted C1-6 heteroalkyls; R6 is OR7 or N3, NH2, NO2 or CN, where R7 is selected from the same group which defines R1-5; R8-9 are independently selected from the group consisting of hydrogen, fluoro, chloro, bromo, iodo, or R6; and a and n are each independently zero or a positive integer.

Abstract: A separation device employing a gas separation filter and swirler vanes for separating gas from a gasliquid mixture is provided. The cylindrical filter utilizes the principle that surface tension in the pores of the filter prevents gas bubbles from passing through. As a result, the gas collects in the interior region of the filter and coalesces to form larger bubbles in the center of the device. The device is particularly suited for use in microgravity conditions since the swirlers induce a centrifugal force which causes liquid to move from the inner region of the filter, pass the pores, and flow through the outlet of the device while the entrained gas is trapped by the filter. The device includes a cylindrical gas storage screen which is enclosed by the cylindrical gas separation filter. The screen has pores that are larger than those of the filters. The screen prevents larger bubbles that have been formed from reaching and interfering with the pores of the gas separation filter.