公开(公告)号：US4814046A

公开(公告)日：1989-03-21

申请号：US217916

申请日：1988-07-12

申请人： Terry R. Johnson ,  John P. Ackerman ,  Zygmunt Tomczuk ,  Donald F. Fischer

发明人： Terry R. Johnson ,  John P. Ackerman ,  Zygmunt Tomczuk ,  Donald F. Fischer

IPC分类号： G21C19/44 ,  C01G56/00 ,  C22B60/02 ,  C22B60/04 ,  G21C19/48 ,  G21F9/06 ,  G21F9/30 ,  C01G57/00 ,  G21C1/24 ,  G21C19/42

CPC分类号： C22B60/04 ,  C22B60/0295 ,  G21C19/48 ,  Y02W30/884

摘要： A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

摘要翻译： 除了稀土和其他裂变产物元素之外，还可以从含有超铀元素的废氯化物电解盐中除去超铀元素的方法，因此可以更容易地处理盐废物，并且可以回收有价值的超铀元素以便再利用。 盐与选择性地从盐中提取超铀元素的镉 - 铀合金接触。 在与Integral Fast Reactor（IFR）相关的核燃料的后处理中产生废盐。

公开(公告)号：US5336450A

公开(公告)日：1994-08-09

申请号：US999339

申请日：1992-12-31

申请人： John P. Ackerman ,  Terry R. Johnson

发明人： John P. Ackerman ,  Terry R. Johnson

IPC分类号： C22B61/00 ,  G21C19/48 ,  G21F9/00

CPC分类号： C22B61/00 ,  G21C19/48 ,  Y02W30/884

摘要： The invention is a process for the removal of rare earths from molten chloride electrolyte salts used in the reprocessing of integrated fast reactor fuel (IFR). The process can be used either continuously during normal operation of the electrorefiner or as a batch process. The process consists of first separating the actinide values from the salt before purification by removal of the rare earths. After replacement of the actinides removed in the first step, the now-purified salt electrolyte has the same uranium and plutonium concentration and ratio as when the salt was removed from the electrorefiner.

摘要翻译： 本发明是从用于综合快堆反应堆燃料（IFR）后处理的氯化氯电解质盐中除去稀土的方法。 该方法可以在电抛光机的正常操作期间连续使用或作为间歇工艺使用。 该方法包括首先通过除去稀土元素将纯化前的锕系元素值与盐分离。 在更换在第一步骤中除去的锕系元素后，现有纯化的盐电解质具有与从电学纯化器中除去盐时相同的铀和钚浓度和比例。

公开(公告)号：US5147616A

公开(公告)日：1992-09-15

申请号：US770387

申请日：1991-10-03

申请人： John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  William E. Miller ,  R. Dean Pierce

发明人： John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  William E. Miller ,  R. Dean Pierce

IPC分类号： C22B60/02 ,  G21C19/48

CPC分类号： C22B60/0213 ,  G21C19/48 ,  Y02P10/212 ,  Y02W30/884

摘要： A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe alloy retains the noble metal fission products and is stored while the Mg is distilled and recycled leaving the transuranium actinide and rare earth fission products isolated.

摘要翻译： 将铀的锕系元素值与含有稀土和贵金属裂变产物的废核氧化物燃料中存在的铀值分离的过程。 在CaCl 2和含有不少于约84重量％铀的U-Fe合金的存在下，在约800℃至约850℃的温度范围内，氧化物燃料用Ca金属还原以产生 溶解在U-Fe合金中的另外的铀金属提高铀浓度并且具有铀锕系金属和稀土裂变产物金属以及其中溶解的贵金属裂变产物。 将碳酸钙和碱金属的裂变产物和碱土金属和碘溶解在其中的CaCl 2分离并用碳电极进行电解处理，以将碳电极转化为CO和CO 2，从而将CaO还原为Ca金属。 Ca金属和CaCl2被再循环以减少额外的氧化物燃料。 具有锕系金属和稀土裂变产物金属的U-Fe合金和溶解在其中的贵金属裂变产物与吸收锕系元素和稀土裂变产物金属的金属Mg接触。 U-Fe合金保留贵金属裂变产物，并在Mg蒸馏和再循环时储存，分离出铀锕系和稀土裂变产物。

公开(公告)号：US5160367A

公开(公告)日：1992-11-03

申请号：US770385

申请日：1991-10-03

申请人： R. Dean Pierce ,  John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  William E. Miller

发明人： R. Dean Pierce ,  John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  William E. Miller

IPC分类号： C22B60/02 ,  G21C19/48

CPC分类号： C22B60/0213 ,  G21C19/48 ,  Y02P10/212 ,  Y02W30/884

摘要： A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg Cl.sub.2 to transfer Mg values from the transport salt to the Cu--Mg alloy while transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy.

摘要翻译： 将铀的锕系元素值与含有稀土和贵金属裂变产物的废核氧化物燃料中存在的铀值分离的过程。 在CaCl 2和Cu-Mg合金的存在下，在约750℃至约850℃的温度范围内，氧化物燃料用Ca金属还原，其含有不低于约25重量％的Mg，以沉淀 铀金属和一些离开Cu-Mg合金的贵金属裂变产物具有铀钛锕金属和稀土裂变产物金属以及一些溶解在其中的贵金属裂变产物。 将碳酸钙和碱金属的裂变产物和碱土金属和碘溶解在其中的CaCl 2分离并用碳电极进行电解处理，以将碳电极转化为CO和CO 2，从而将CaO还原为Ca金属。 Ca金属和CaCl2被再循环以减少额外的氧化物燃料。 将具有锇金属和稀土裂变产物金属的Cu-Mg合金以及溶解在其中的贵金属裂变产物与包含Mg Cl 2的运输盐接触，以将Mg值从运输盐转移到Cu-Mg合金，同时穿过锕系和稀有金属 土壤裂变产物金属从Cu-Mg合金转移到运输盐。 然后将输送盐与Mg-Zn合金混合，将Mg值从合金转移到运输盐，同时溶解在盐中的铀锕系和稀土裂变产物值被还原并转移到Mg-Zn合金中。

公开(公告)号：US5141723A

公开(公告)日：1992-08-25

申请号：US770386

申请日：1991-10-03

申请人： William E. Miller ,  John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  R. Dean Pierce

发明人： William E. Miller ,  John P. Ackerman ,  James E. Battles ,  Terry R. Johnson ,  R. Dean Pierce

IPC分类号： C22B60/02 ,  G21C19/48

CPC分类号： G21C19/48 ,  C22B60/0213 ,  Y02W30/884

摘要： A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.

摘要翻译： 公开了将铀的锕系元素值与含有稀土和贵金属裂变产物以及其它裂变产物的废核氧化物燃料中存在的铀值分离的方法。 在氯化钙和U-Fe合金存在下，氧化物燃料在大约800℃下液化，以溶解铀金属和贵金属裂变产物金属和铀锕系金属和稀土裂变产物金属 留下具有CaO的氯化钙和碱金属的裂变产物和溶解在其中的碱土金属和碘。 其中所含的氯化钙和CaO及其裂变产物与U-Fe合金分离，金属溶解在其中。 其中溶解有来自废核燃料的还原金属的U-Fe合金与一种或多种选自碱金属或碱土金属和Fe或U卤化物的碱金属或碱土金属卤化物的混合物接触，或者 其组合将铀锕系金属和稀土金属转移到离开铀的卤化物盐和U-Fe合金中的一些贵金属裂变产物，然后从U-Fe合金中分离卤化物盐和溶解在其中的铀钛金属， 金属溶解在其中。

公开(公告)号：US5055813A

公开(公告)日：1991-10-08

申请号：US544987

申请日：1990-06-28

申请人： Terry R. Johnson

发明人： Terry R. Johnson

IPC分类号： H01F13/00

CPC分类号： H01F13/00

摘要： A compact, portable magnetization/demagnetization device comprises a tubular housing internally of which at one end is mounted an electrical coil which surrounds a cavity accessible to screwdrivers and the like. At the opposite end of the housing there is mounted a pair of AC prongs. A manually operated switch on the housing permits the coil to be energized when the prongs are energized to establish a magnetic field in the cavity for the purpose of magnetizing and demagnetizing tools and other objects.

摘要翻译： 紧凑的便携式磁化/消磁装置包括内部的管状壳体，其内部安装有围绕螺丝刀等可接近的空腔的电线圈。 在外壳的另一端安装了一对交流插脚。 壳体上的手动开关允许线圈在通电时通电，以在腔中建立磁场，以便磁化和消磁工具和其它物体。

公开(公告)号：US4032615A

公开(公告)日：1977-06-28

申请号：US651981

申请日：1976-01-27

申请人： Terry R. Johnson

发明人： Terry R. Johnson

IPC分类号： C01D1/04 ,  C01D

CPC分类号： C01D1/04

摘要： Alkali metals such as those employed in liquid metal coolant systems can be safely reacted to form hydroxides by first dissolving the alkali metal in relatively inert metals such as lead or bismuth. The alloy thus formed is contacted with a molten salt including the alkali metal hydroxide and possibly the alkali metal carbonate in the presence of oxygen. This oxidizes the alkali metal to an oxide which is soluble within the molten salt. The salt is separated and contacted with steam or steam-CO.sub.2 mixture to convert the alkali metal oxide to the hydroxide. These reactions can be conducted with minimal hydrogen evolution and with the heat of reaction distributed between the several reaction steps.

公开(公告)号：US07685785B2

公开(公告)日：2010-03-30

申请号：US11268882

申请日：2005-11-08

申请人： Terry R. Johnson

发明人： Terry R. Johnson

IPC分类号： E04B5/00

CPC分类号： E04D12/002

摘要： An underlayment sheet (10, 10′) is applied in overlapping courses to a roof deck (36) for establishing a weather-resistant membrane for use as a final exposed surface or below a roof covering (50). The underlayment sheet (10, 10′) has a bottom surface (16, 16′) to which a pressure sensitive adhesive section (22, 22′) is applied generally continuously along its length. A non-adhesive section (24, 24′) also extends the length of the bottom surface (16, 16′) adjacent its upper long edge (18, 18′) for providing a contact surface with the roof deck (36) which is devoid of any adhesive material. The non-adhesive section (24, 24′) is attached to the roof deck (36) using tin tags (44, 44′) or other mechanical fastening components. When subsequent underlayment sheets (10, 10′) are applied in overlapping courses, the adhesive sections (22, 22′) bond over the preceding underlayment sheet (10, 10′) to establish a water tight seal. The top surface (14) of the underlayment sheet (10) may include a supplemental bonding strip (30) which adheres directly to the adhesive section (22) of an overlying underlayment sheet (10) to establish a tenacious seal. The top surface (14′) may also be impregnated with a course granular material (52) to serve as a final, exposed surface for the roof in lieu of shingles or the like. If a future re-roofing operation is required, the subject underlayment system can be removed from the roof deck (36) without damaging or delaminating the roof deck (36) material.

摘要翻译： 将覆盖层（10,10'）以重叠的路线施加到屋顶板（36），以建立用作最终暴露表面或屋顶覆盖物（50）下方的耐候性膜。 所述垫片（10,10'）具有底表面（16,16'），压敏粘合剂部分（22,22'）通常沿其长度连续地施加到该底表面上。 非粘合部分（24,24'）还延伸邻近其上长边缘（18,18'）的底表面（16,16'）的长度，以提供与顶板（36）的接触表面， 没有任何粘合剂材料。 非粘合部分（24,24'）使用锡标签（44,44'）或其它机械紧固部件附接到屋顶板（36）。 当后续的支撑片（10,10'）以重叠的路线施加时，粘合剂部分（22,22'）结合在先前的垫片（10,10'）上以建立防水密封。 垫片（10）的顶表面（14）可以包括补充粘合条（30），其直接粘附到覆盖的底片（10）的粘合部分（22）上以建立坚固的密封。 顶表面（14'）也可以用过程颗粒材料（52）浸渍，以用作屋顶的最终的暴露表面，以代替屋顶板等。 如果需要进行未来的再屋顶操作，则可以从屋顶板（36）上拆除受试者支撑系统，而不会损坏屋顶板（36）材料。

公开(公告)号：USH1227H

公开(公告)日：1993-09-07

申请号：US744753

申请日：1991-08-14

申请人： Michele A. Lewis ,  Terry R. Johnson

发明人： Michele A. Lewis ,  Terry R. Johnson

IPC分类号： G21F9/12 ,  G21F9/16 ,  C21F9/16

CPC分类号： G21F9/12 ,  G21F9/162

摘要： The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.