Abstract: An apparatus, transfer cask, system, and method for defueling a nuclear reactor and transferring spent nuclear fuel from a spent nuclear fuel to a storage cask for long terms storage. In one aspect, the invention is an apparatus for use in transferring a canister of spent nuclear fuel from a transfer cask to a storage cask, the apparatus comprising a radiation absorbing shield surrounding a portion of a hole through which the canister can pass; means for securing the apparatus to the top surface of the storage cask; means for securing the bottom surface of the transfer cask to the apparatus; wherein the transfer cask securing means and the storage cask securing means are positioned on the apparatus so that when the apparatus is secured to both the transfer cask and the storage cask, the cavity of the transfer cask, the hole, and the cavity of the storage cask are substantially aligned; and means for moving the bottom lid in a horizontal direction once the bottom lid is unfastened from the bottom surface.

Abstract: An apparatus and method for stabilizing a spent nuclear fuel containment cask so as to prevent tipping under design basis earthquake conditions. In one aspect, the apparatus comprises a lamina and a slid plate in surface contact with the lamina, forming a slidable interface; wherein the slidable interface has a coefficient of friction within a range resulting in an acceptable level of net horizontal displacement of a cask resting on the apparatus under design basis earthquake conditions.

Abstract: A system and method for transferring a canister of spent nuclear fuel from a transfer cask to a receiving cask. In one aspect, the system comprises a below grade opening adapted for receiving a cask; a platform positioned within the opening, the platform capable of vertical movement; and at least two jacks for vertically moving the platform; wherein the platform is capable of lowering the cask within the opening.

Abstract: An apparatus, system, and method of storing and transferring a canister of spent nuclear fuel. In one aspect, the apparatus is a lid for a ventilated vertical overpack having a chamber for receiving spent nuclear fuel, the lid having ventilation ducts. In one aspect, the system comprises: a lid for a ventilated vertical overpack having a chamber for receiving spent nuclear fuel, the lid having ventilation ducts; and a ventilated vertical overpack having a cylindrical body including lower ventilation ducts, a bottom, and a chamber formed by the body and the bottom adapted for receiving a canister of spent nuclear fuel.

Abstract: An apparatus, transfer cask, system, and method for defueling a nuclear reactor and transferring spent nuclear fuel from a spent nuclear fuel pool to a storage cask for long terms storage. In one aspect, the invention is an apparatus for use in transferring a canister of spent nuclear fuel from a transfer cask to a storage cask, the apparatus comprising a radiation absorbing shield surrounding a portion of a hole through which the canister can pass; means for securing the apparatus to the top surface of the storage cask; means for securing the bottom surface of the transfer cask to the apparatus; wherein the transfer cask securing means and the storage cask securing means are positioned on the apparatus so that when the apparatus is secured to both the transfer cask and the storage cask.

Abstract: A power plant apparatus comprising a condenser for condensing turbine exhaust steam having a steam dome, a steam inlet, a tube bundle, a hot well for collecting condensate, an air removal section, an internal makeup water heater bundle. An internal makeup water header which includes a pipe having spray nozzles arranged counter-current to the flow of steam introduced by the steam inlet is used to introduce heated makeup water into the exhaust stream from the turbine within the condenser.

Abstract: An apparatus and method for maximizing the radiation shielding for spent nuclear fuel during cask transfer procedures. In one aspect, the method comprises submersing an apparatus having a jacket and a cavity for receiving spent nuclear fuel into a pool, wherein the jacket is empty and hermetically sealed; placing spent nuclear fuel into the cavity of the apparatus; lifting the apparatus from the pool; placing the apparatus in a staging area; filling the jacket with neutron absorbing liquid; draining the pool water from the cavity; and lifting the apparatus from the staging area.