Abstract: In treatment of aqueous solutions and suspensions of radioactive waste through a step of drying and pulverizing the aqueous solutions and suspensions and a successive step of compressing and solidifying the resulting powders of radioactive waste, a step of measuring a water content of the powders is provided between the step of drying and pulverizing and the step of compressing and solidifying. When the measured water content of the powders fails to satisfy a predetermined water content, the powders are eliminated from a system of the treatment without passing through the step of compressing and solidifying.

Abstract: In a process for treating radioactive liquid waste having an evaporation concentration device, including a concentration vessel, and a steam heater having steam inlet and outlet lines and operating to heat, with heating steam, radioactive liquid waste in the evaporation concentration device so as to concentrate the waste, contamination of the entire steam heater system in the event of leakage is prevented or greatly reduced by the provision of: (1) a sluice valve in the steam outlet line near the heater; (2) a discharge line with a drain valve for discharging any waste fluid between the heater and the sluice valve; and (3) means for receiving radioactive waste discharged through the discharge line. In accordance with the process of the present invention, when the pressure within the steam heater is less than that within the concentration vessel, and the operation of the evaporation concentration device is to be resumed, the sluice valve is first closed and the drain valve is opened.

Abstract: There is disclosed a process for the production of solid particles of bioinjurious waste, e.g., radioactive concentrates, wherein a liquid, and in a given case a binder containing waste is divided into drops and supplied energy in a gaseous medium, the liquid is evaporated and the drops form solid particles. There is supplied carrier free energy to at least partially vaporize the liquid of the drops, in a given case under reduced pressure and in a given case with a binder forming solid particles from the drops.

Abstract: An inert carrier process for drying radioactive waste material and for incorporating the dry material into a binder from which the dried material will not be leached is disclosed. In this process, a hot inert liquid carrier is provided into which the solution to be dried is introduced under extremely turbulent conditions. The solvent flashes off leaving the dried particles dispersed in the inert carrier which carries these particles to a mixing station where a binder for the particles is injected under turbulent conditions. The binder preferentially wets the particles and the coated particles are carried to a separator section where the binder coated particles coalesce and separate from the carrier as a second phase. Thereafter a curing agent can be added to the binder.

Abstract: A municipal water supply system for providing potable water under pressure from sea water including a nuclear reactor heated boiler for raising the temperature of sea water to at least 250.degree. F and at superatmospheric pressure means for conveying the superheated steam to an expansion turbine, whereby the superheated steam drives the turbine while the temperature of the steam is reduced to about the boiling point of water at atmospheric pressure, a heat exchanger for condensing the exhaust from the turbine while simultaneously preheating incoming sea water to the system, and liquid pumping means driven by the expansion turbine for conveying the condensed water under pressure to a municipal distribution system. Additionally, means are provided for controlling the temperature within the boiler chamber by controlling the volume of incoming sea water.

Abstract: A system for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate.

Abstract: A float valve arrangement is disposed in a mixing condenser that is arranged intermediate the first and second stage of a two-stage evaporation installation suitable for purifying radio-active liquids. In normal operation, vapor evaporated in the first stage extends via a first conduit into the mixing condenser where such vapor is condensed by contact with a portion of the liquid in the second stage that is circulated back to the mixing condenser via a pump. The normal vapor pressure generated in the first stage keeps the float valve open and permits the steam to displace, into the second stage, liquid present in the mixing condenser. During start-up and shutdown of the installation wherein vapor from the first stage is no longer present, the resulting rise in liquid level in the mixing condenser causes the float valve to close and to prevent any backflow of liquid into the first stage via the first conduit.

Abstract: A method of and apparatus for the purification of a liquid contaminated with radioactive substances, wherein the liquid is infed to an evaporator in or with which there is connected a column having a multiplicity of superposed plates or floors. The vapor generated in the evaporator is guided through a washing or scrubbing liquid uniformly distributed at the floors and flowing in crosswise counterflow with regard to the vapor. The washing liquid at the floors is deflected a number of times in such a manner that the washing liquid itself and together with the droplets entrained by the vapor is uniformly admixed and the washing liquid subjected to a constant intake of the radioactive substance.

Abstract: A falling film evaporator including a vertically oriented pipe heated exteriorly by a steam jacket and interiorly by a finned steam tube, all heating surfaces of the pipe and steam tube being formed of a material wet by water such as stainless steel, and packing within the pipe consisting of Raschig rings formed of a material that is not wet by water such as polyvinylidene fluoride.

Abstract: An evaporation system for radioactive waste concentration comprises an evaporation chamber, a heat exchanger, and a circulation pump arranged in an upstanding spaced-apart configuration and enclosed within a radiation shield whereby access to the system is limited and frequently only possible from overhead. The steam chest of the heat exchanger is suspended from a removable top plate to allow removal for repair or replacement without exposing maintenance personnel to radiation. A novel circulation pump having a vertical shaft and propeller supported from a top plate which can be removed from overhead also allows maintenance or replacement of the pump without exposure to radiation or having to drain the system.