ML20133K224
| ML20133K224 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 01/21/1957 |
| From: | Belmore F MALLINCKRODT, INC. |
| To: | Johnson L US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20133G976 | List:
|
| References | |
| FOIA-96-343 NUDOCS 9701210155 | |
| Download: ML20133K224 (3) | |
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- .L _ : 4 January 21, 1957 s
}k. Lyall Johnson, Chief Licensing Division Division of Civilian Application
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U. S. Atomic Energy Commission f'
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Washington 25, D. C.
Dear Fr.. Johnson:
Reference is made to our License SNM-33 as revised which permits us to receive and possess uranium enriched in the U-235 isotope for use in making uranium oxides. We hereby request that SNM-33 be further revised to permit us to receive and possess uranium enriched in the U-235 isotope for use in making Uranyl Sulfate as described in the attachment.
The ope rations described in the attachment will be carried out at our Hematite, Missouri plant where all general procedures and equip-ment for control of health and safety, material and criticality out-lined in previous applications will be applicable. The process as described will be utilized for material enriched to approximatelj For fully enriched material, we would propose the 20% in U-235.
same process with the exception that no mixing of batches would be permitted and the 0.7 pound batch size would be maintained through-out the process.
We trust that the information contained herein will be adequate to permit you to issue the necessary revision to our license. As you doubtless know, we are presently negotiating with representatives of the Japanese and Danish Governments for the conversion of 20% UF6 to Uranyl Sulfate for reactors which they are purchasing from the Atomics International Division of North American Aviation.
0' Very truly yours, 9
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y Frederick H. Belmore
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Special Asst. to the President FMB/ck
\\j Attachment City of St. Louis Notary M d "
- W State of Missouri Subscribed and sworn to before me this.f/ day of 1957
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- l'. 1391 14 ATTliCIC12T TO AFrL1ClT10M DATED JAH. 21, 1957 AR RtN1310N TO LlCE!GE SN!!-33 SUBJIET : General Procedure for the Preparation of Uranyl Sulfate from Uranium Hexafluoride of Approximately 20f, U-235 Content.
The steps involved in the production of uranyl sulfate from uranium hexafluoride are as follows:
- 1. Hydrolysis of UF6
- 2. Precipitation of Ammonium Diuranate
- 3. Filtration
- 4. Drying
- 5. Decomposition to U 0g 3
- 6. Milling U 03g
- 7. Transfer of U 03g
- 8. Preparation or uranyl sulfate solution
- 9. Evaporation
- 10. Drying of uranyl sulfate
- 11. Grinding
- 12. Packaging The operations 1 through 5 vill be the sane as that used in the pro-ceos to produce weapons-grade uranium dioxide. The batch size through these steps vill be 318 grams (0.7 lb.) of uranium which is limited j
by the equipment size.
The U 0g vill be transferred in covered trays from the decomposition 3
furnace to the transfer dry box. Here four batches will be mixed and placed in a stainless steel ball mill container of "always safe" de-sign, five inches in diameter. The ball mill, properly sealed, will be removed from the dry box and put into position on the ball mill drive. This equipment will be mounted under the transfer dry box (or other suitable position).
Following this operation the ball mill vill be returned to the trans-fer dry box and the U 03 g transferred to a tared polyethylene bottle and weighed. 1 mavhm of 1600 grams U 03 g (1360 gU) vill be placed in this bottle.
The bottle containing the U 0g is next transferred to a large hood 3
which vill serve as a process hood for the uranyl sulfate prepara-j is transferred to a three liter distillation tion. Here the U 03g nask. The transTer vill be made using a nexible plastic tube attached to the neck of the polyethylene bottle and extending down into the distillation 11ask. A rubber sleeve on the ilexible tubing vill serve as a dust-tight seal at the opening of the nask.
o A separatory runnel is connected through a rubber stopper to the neck of the d1stillation flank. Addition of reagents such as sulfuric ac11 wd1 be made throu ;c this separatory funne1. The distillation arm of the flask will be conrected to a water cooled condenser. The distdlate w21] be caugnt in a suitable container. It will be tested for uranium, and if any is found, will be recovered by standard methods.
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The distillation :'lask will be heated by a heating mantle clad with stainless etcel chect. The heating mantle and distillation flask will be enclosed in a stainless steel tank of suitablo size as a prevention against loss if the glassware should break.
i The uranyl sulfate solution precered in the flask is then transferred to two Pyrex trays (8" x 11/2") located in the same hood, but two feet away. These Pyrex trays are placed in a stainless steel tray (24" x 36" x 4") located on top of a hotplate of the same size. The evaporation of the uranyl sulfate to near dryness will be carried out in this equipment. Approximately one inch above the Pyrex trays will be suspended a stainless steel sheet (18" x 24" x 1/16"). This will serve to prevent loss of uranyl sulfate during the evaporation pro-cess.
Because of equipment limitations there will be no more than two batches in this hood at one time, one in the distillation flask and one in the eveporation trays.
The uranyl sulfate is then transferred to stainless steel drying trays of "always safe" design and the trays are transferred to the drying ovens for necessary drying.
The dr.ied uranyl sulfate is taken to the transfer dry box at a time when U 0g is not in this hood. The material is ground in a stain-3 less steel try with a stainless steel rolling pin.
ilhile still in the transfer dry box, the material is packaged in i
polyethylene bottles of " safe design", and then stored in a " bird-i cage" for shipment to the customer.
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