US2793753A

US2793753A - Removal of material from processing tanks

Info

Publication number: US2793753A
Application number: US588058A
Authority: US
Inventors: Donald S Webster
Original assignee: Individual
Current assignee: Individual
Priority date: 1945-04-12
Filing date: 1945-04-12
Publication date: 1957-05-28
Anticipated expiration: 1974-05-28

Description

y 1957 D. s. WEBSTER 2,793,753

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v IN Dona/0 S. Webs fer United States Patent 2,793,753 REMOVAL OF MATERIAL FROM PROCESSING TANKS Donald S. Webster, Richland, Wash, assignor to the 5 United States of America as represented by the United States Atomic Energy Commission Application April 12, 1945, Serial No. 588,058 1 Claim. (Cl. 210-153) The present invention relates to a procedure for the removal of radioactive materials, and more particularly it concerns the removal of radioactive substances from apparatus by remote control methods wherein such substances have been produced as a result of the fission of a uranium isotope by means of slow or thermal neutrons.

Removal of such radioactive substances involves certain difliculties peculiar thereto in that the entire apparatus is located within very massive shielding barriers and must be accomplished without the operators having close or even visual access to the equipment. Moreover, the nature of the processing equipment is such that heretofore known methods of removing solids from a processing tank are neither practical nor appropriate. This arises from the physical arrangement of the equipment within the shielding barriers; simple methods of slurrying the radioactive solids up out of the processing tank or vessel have not been found practical or possible. The present invention provides a way of removing the radioactive solids from the processing tank which overcomes the objections otherwise faced, which minimizes the need for close operator attention and observation and which obviates the need for a separate opening in the lower part of the processing tank for the removal of these solids. The objectives of the invention are achieved by the adaptation of a gas or vapor lift to the processing tank whereby the radioactive fission products remaining in the tank at the end of a processing run can be slurried and pumped upwardly out of the tank by means of the vapor lift. The vapor lift adapts itself very well to utilization in this combination and minimizes the ditficulties attendant to the handling or removing of the radioactive material.

It is an object of the present invention to provide a safe, efiicient, and easily operated method and apparatus for the disposal of radioactive fission products subsequent to the separation of plutonium therefrom.

It is a further object of this invention to provide a process wherein such fission products can be readily removed by remote control means through the use of a relatively simple and easily operated apparatus.

Another object of the invention is to provide a system for removing solid material, particularly radioactive fission fragments, from a chemical processing tank comprising means forming a vapor lift extending into the tank and means for admitting liquid and slurrying the material to facilitate its being pumped by the vapor lift.

Other objects of the present invention will be apparent as the description proceeds.

The present invention provides a method and apparatus for disposing of fission products after plutonium has been separated therefrom, which involves first contacting a solution containing said fission products and plutonium with a suitable adsorbent material, such as a base exchange resin, for example, Amberlite IR-l which is a condensation product of a polyhydric phenol and formaldehyde having methylene sulfonic acid groups incorporated therein to increase the exchange at low pH. Thereafter, the resulting adsorbate is treated with an elutp 2,793,753 Patented May 28, 1957 See ing agent that is substantially specific to plutonium whereby the latter is desorbed leaving the radioactive fission products remaining on the adsorbent. The latter, containing the aforesaid radioactive fission products, can be conveniently removed from the containing vessel by means of an air lift after which a fresh supply of adsorbent is introduced and additional solution containing fission products and plutonium treated as described. In this connection other inert gases, such as for example, nitrogen, carbon dioxide, and the like, may be used in place of air as a means of forcing the radioactive resin out of the containing vessel. The radioactive material thus removed may be conveyed to an underground vault or other suitable storage where it is permitted to remain until the intensity of the radioactivity has diminished to such an extent that those coming into contact therewith are not physically endangered by the handling thereof.

While the present invention is adapted to the removal of substantially any radioactive material carried on a suitable adsorbent therefor, it is particularly applicable to the removal and disposal of the radioactive fission products present in solutions of uranyl nitrate, prepared by dissolving neutron-irradiated uranium in nitric acid.

A preferred embodiment of the present invention, and which will be more completely understood by reference. to the accompanying drawing involves first introducing a 10% aqueous solution of uranyl nitrate, containing plutonium and fission products, into head tank 4, equipped with vent pipe 6 and overflow pipe 5, from tank 1 through pipe 2 by means of steam jet 3. From head tank 4 the solution is flowed downwardly through connecting pipe 7 into tower 23 containing base-exchange Amberlite resin IR-l, 8 supported on a filter comprising layer of stainless steel shot 9 having varying diameters of one-sixteenth, one-eighth and one-fourth inch supported on perforated stainless steel disc 34. From tower 23 the solution of uranyl nitrate, now free from plutonium, flows through pipe 10 into catch tank 11 equipped with overflow pipe 13 and outlet pipe 15 to which is affixed steam jet 16 for transferring the liquid to a suitable container or Waste tank 14. The adsorbent 8, containing the adsorbed UO2++ ions and plutonium, in order to remove the UO2++ ions, is washed with 0.25 MH2SO4 introduced from tank 28 outside of concrete wall 35 by means of valve 21 through pipe 30 into head tank 4 then into pipe 7 and tower 23. The extract solution is caught in tank 11 and transferred to tank 14 by means shown. The adsorbent is next washed with 1.25 M sodium bisulfate contained in tank 29 and flowed as indicated for the sulfuric acid solution to recover the plutonium. This extract solution containing the plutonium is recovered in tank 11 and transferred by means of pipe 17 equipped with steam jet 18 to tank 19.

As a result, the adsorbent is substantially free of plutonium and UOz++ ions. However, it is contaminated with highly radioactive fission products which must be removed without endangering operating personnel. This object is accomplished by means of an air lift system which functions as follows, reference being made to the accompanying drawing: Water is introduced into pipe 7 and tower 23 from tank 1 through pipe 2 by means of steam jet 3 to a predetermined level in connecting pipe 7 depending on the height through which the liquid is discharged, this height generally being /3 to /2 of the distance of the overall lift. Air, or other suitable inert gas, is next passed upwardly through pipe 22 from pipe 20, controlled by valve 33, by means of foot 32. As a result of the bubbling action, the density of the liquid contained in pipe 22 is reduced and forced in an upwardly direction by the liquid medium of greater density which surrounds and is in communication with the submerged end of pipe 22. Under such conditions the adsorbent 8 forms a slurry in vessel 23 and is forced upwardly through pipe 22 into tank 24 equipped with vent 25, from which it flows downwardly through pipe 26 into container 27. If desired, water may be admitted into the bottom of vessel 23 at a point just above shot layer 9 through pipe 31 for the purpose of producing a slurry with said adsorbent. Fresh adsorbent resin for a subsequent run is introduced from hopper 36 into pipe 37 where a slurry thereof is formed with the water entering from nozzle 38. The stream of water coming from nozzle 38 strikes venturi 39 causing a partial vacuum in the line leading to hopper 36 thereby aiding in the feeding of the resin into pipe 37 from which the slurry is conducted into tank 4 and thereafter introduced into tank 23. If desired, cover 40 may be removed and entry made into the interior of the concrete enclosure in order to repair the apparatus or for other purposes. Prior to entering said enclosure, however, it is necessary to Wash out the apparatus, which is preferably constructed of stainless steel, with a solution capable of removing the radioactivity therefrom, such as for example, dilute solutions of nitric or hydrofluoric acids or mixtures thereof.

It will be apparent to those skilled in the art that the process and apparatus generally set forth above are susceptible of numerous modifications without departing from the scope of this invention. It is, therefore, to be strictly understood that any such modifications are re garded as lying within the scope thereof.

I claim:

Apparatus for processing a liquid material containing radioactive fission products, comprising an enclosure of radiation shielding material, an ion exchange reaction tower disposed vertically within said enclosure, filter means comprising metal shot forming a layer at the bottom of said column, a second layer formed of a solid absorbent material disposed directly above and supported by said bottom layer, said absorbent material being capable of absorbing radioactive fission products from a process liquid filtered therethrough, said tower having an opening near the top thereof for the entrance of the liquid material to be processed, and having an outlet at the bottom thereof for the removal of said liquid after processing, a hollow tube extending downwardly into said tower from the top thereof to a point adjacent the top of said filter means, an injector for admitting gas into the lower end of said tube, and a water pipe terminating in said layer of absorbent material at a point adjacent the end of said tube.

References Cited in the file of this patent UNITED STATES PATENTS 1 660,946 Butler Oct. 30, 1900 1,042,189 Beduwe Oct. 22, 1912 1,316,507 Pollard Sept. 16, 1919 1,444,921 Hunter Feb. 13, 1923 1,512,561 Oliphant Oct. 21, 1924