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1. 发明申请

US20090104111A1 Carbonate Thermochemical Cycle for the Production of Hydrogen 失效
标题翻译：碳酸氢盐生产氢化学循环
公开(公告)号：US20090104111A1
公开(公告)日：2009-04-23
申请号：US11874958
申请日：2007-10-19
申请人： Jack L. Collins , Leslie R. Dole , Juan J. Ferrada , Charles W. Forsberg , Marvin J. Haire , Rodney D. Hunt , Benjamin E. Lewis, JR. , Raymond G. Wymer
发明人： Jack L. Collins , Leslie R. Dole , Juan J. Ferrada , Charles W. Forsberg , Marvin J. Haire , Rodney D. Hunt , Benjamin E. Lewis, JR. , Raymond G. Wymer
IPC分类号： C01B3/02
CPC分类号： C01B3/02 , C01B3/063 , C01B13/0203 , Y02E60/36
摘要： The present invention is directed to a thermochemical method for the production of hydrogen from water. The method includes reacting a multi-valent metal oxide, water and a carbonate to produce an alkali metal-multi-valent metal oxide compound, carbon dioxide, and hydrogen.
摘要翻译：本发明涉及从水中生产氢的热化学方法。该方法包括使多价金属氧化物，水和碳酸盐反应，生成碱金属 - 多价金属氧化物，二氧化碳和氢。

2. 发明申请

US20110067398A1 CONCENTRATED SOLAR POWER SYSTEM 有权
标题翻译：集中式太阳能发电系统
公开(公告)号：US20110067398A1
公开(公告)日：2011-03-24
申请号：US12886039
申请日：2010-09-20
申请人： Alexander H. Slocum , Jacopo Buongiorno , Charles W. Forsberg
发明人： Alexander H. Slocum , Jacopo Buongiorno , Charles W. Forsberg
IPC分类号： F03G7/00 , F24J2/38 , F24J2/30 , F24J2/04 , F03G6/06
CPC分类号： F24S10/13 , F24S10/90 , F24S20/20 , F24S23/70 , F24S40/10 , F24S60/00 , F28D20/0039 , F28D20/02 , F28D20/028 , F28D2020/0047 , F28D2020/0095 , Y02E10/41 , Y02E10/44 , Y02E10/46 , Y02E60/145 , Y02E70/30 , Y02P90/50
摘要： Systems and methods for concentrating and storing solar energy are provided. A solar energy receiver for use with the systems and methods may include a container for holding a solar absorption material, such as a phase change material, and a cooled cover disposed above the container for condensing and collecting vaporized phase change material collected along an underside of the cover.
摘要翻译：提供了集中和储存太阳能的系统和方法。与系统和方法一起使用的太阳能接收器可以包括用于容纳太阳能吸收材料（例如相变材料）的容器，以及设置在容器上方的冷却盖，用于冷凝和收集沿着下部收集的蒸发的相变材料封面。

3. 发明授权

US5076999A Passive decay heat removal system for water-cooled nuclear reactors 失效
标题翻译：水冷核反应堆被动衰变散热系统
公开(公告)号：US5076999A
公开(公告)日：1991-12-31
申请号：US596155
申请日：1990-10-10
申请人： Charles W. Forsberg
发明人： Charles W. Forsberg
IPC分类号： G21C15/18
CPC分类号： G21C15/18 , Y02E30/40
摘要： A passive decay-heat removal system for a water-cooled nuclear reactor employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated box located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.
摘要翻译：用于水冷核反应堆的被动衰变 - 热去除系统采用封闭的传热回路，其中热交换线圈位于反应堆内部的开口绝缘箱内，低于其正常水位，与冷凝器连通位于遏制外面并暴露在大气中。传热回路定位成使得蒸发器处于这样的位置：当反应器中的水位下降时，它将变得暴露在蒸汽中。在蒸发器中产生的蒸汽向上通向冷凝器高于正常水位。在操作中，冷凝器中的冷凝物从系统中除去热量，冷凝的液体返回到蒸发器。该系统被布置成使得在水位处于其通常位置的正常反应堆操作期间，将很少的热量从系统中移除，但是在紧急情况下，在低水位条件下，大量的衰变热将被去除。

4. 发明授权

US5613241A Treatment of halogen-containing waste and other waste materials 失效
标题翻译：处理含卤素废物和其他废料
公开(公告)号：US5613241A
公开(公告)日：1997-03-18
申请号：US443624
申请日：1995-05-18
申请人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
发明人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
IPC分类号： G21F9/30 , G21F9/34 , G21F9/00
CPC分类号： C03C1/002 , G21F9/305 , G21F9/34
摘要： A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.
摘要翻译：一种处理含卤素废料的方法。该方法提供了含有能够与废料中的卤素反应的牺牲金属氧化物的熔融玻璃浴。相对于废料中的卤素，牺牲金属氧化物以至少化学计量的量存在于熔融玻璃中。将废料引入熔融玻璃浴中，引起废料中的卤素与牺牲金属氧化物之间的反应，得到金属卤化物。金属卤化物是在熔融玻璃的温度下的气体。将气态金属卤化物与熔融玻璃分离，并与碱金属氢氧化物的水性洗涤剂溶液接触，得到金属氢氧化物或含金属氧化物的沉淀物和可溶性碱金属卤化物。然后将沉淀物与水性洗涤器溶液分离。将含有经处理的废料的熔融玻璃作为废玻璃从浴中除去。本发明的方法可用于处理所有类型的废物，包括放射性废物。该方法特别适用于将卤素从含卤素废物中分离出来。

5. 发明授权

US5832392A Depleted uranium as a backfill for nuclear fuel waste package 失效
标题翻译：废弃的铀作为核燃料废物包装的回填
公开(公告)号：US5832392A
公开(公告)日：1998-11-03
申请号：US858189
申请日：1997-04-15
申请人： Charles W. Forsberg
发明人： Charles W. Forsberg
IPC分类号： G21F1/08 , G21F5/008 , G21F9/36 , G21F9/00
CPC分类号： G21F5/008 , G21F1/085 , G21F9/36 , G21Y2004/60
摘要： A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.
摘要翻译：一种用于在地质储存库中长期处置废核燃料的方法。至少有一个废核燃料组件首先被放置在未密封的废料包装中，并且废弃的铀填充材料被添加到废物包装中。贫化铀填充材料包括具有足以基本上填充组件内部和周围的任何空隙的尺寸的可流动颗粒，并且含有+4价态的同位素贫化的铀的量足以抑制废核燃料从组件溶解到周围的介质，并在废物包装故障的情况下减少储存库内的核危害的可能性。最后，废物包装被密封，从而大大减少放射性核素释放到周围介质中，同时提供辐射屏蔽和增加废物包装的结构完整性。

6. 发明授权

US4106154A Adhesive applicator device 失效
标题翻译：粘合剂涂布器
公开(公告)号：US4106154A
公开(公告)日：1978-08-15
申请号：US686136
申请日：1976-05-13
申请人： Charles W. Forsberg
发明人： Charles W. Forsberg
IPC分类号： A47L13/46 , B05C17/00 , B43M11/04
CPC分类号： A47L13/46 , B05C17/00 , B43M11/04
摘要： An adhesive applicator device including an elongated shaft having a bifurcated end portion and a handle secured thereto at its end opposite the bifurcated end portion. A porous resilient applicator pad is pressed into the bifurcation in the bifurcated portion of the shaft, and includes a central pad portion disposed between the portions of the shaft defining the bifurcation, and a pair of spaced adhesive applicator portions disposed on opposite sides of the central pad portion and exposed to facilitate application of adhesive from the outer peripheral surface of the pad to an object in contact therewith.
摘要翻译：一种粘合剂施加装置，包括具有分叉端部的细长轴和在其分叉端部相对的端部固定到其上的手柄。多孔弹性施加器垫被压入轴的分叉部分中的分叉，并且包括设置在限定分叉的轴的部分之间的中心衬垫部分，以及一对间隔开的粘合剂施加器部分，设置在中心部分的相对侧上并且暴露以便于将粘合剂从垫的外周表面施加到与其接触的物体。

7. 发明授权

US06811745B2 Manufacture of annular cermet articles 失效
标题翻译：制造环形金属陶瓷制品
公开(公告)号：US06811745B2
公开(公告)日：2004-11-02
申请号：US10345539
申请日：2003-01-16
申请人： Charles W. Forsberg , Vinod K. Sikka
发明人： Charles W. Forsberg , Vinod K. Sikka
IPC分类号： B22F312
CPC分类号： F41H5/0414 , B22F7/08 , B22F2998/00 , B22F2999/00 , B22F3/17 , B22F3/18 , B22F3/1208
摘要： A method to produce annular-shaped, metal-clad cermet components directly produces the form and avoids multiple fabrication steps such as rolling and welding. The method includes the steps of: providing an annular hollow form with inner and outer side walls; filling the form with a particulate mixture of ceramic and metal; closing, evacuating, and hermetically sealing the form; heating the form to an appropriate temperature; and applying force to consolidate the particulate mixture into solid cermet.
摘要翻译：制造环形金属包覆金属陶瓷部件的方法直接产生形式并避免了多个制造步骤，例如轧制和焊接。该方法包括以下步骤：提供具有内壁和外侧壁的环形中空形状; 用陶瓷和金属的颗粒混合物填充形式; 关闭，撤离和密封密封; 将形式加热到适当的温度; 并施加力以将颗粒混合物固结成固体金属陶瓷。

8. 发明授权

US5961679A Recovery of fissile materials from nuclear wastes 失效
标题翻译：从核废料中回收裂变材料
公开(公告)号：US5961679A
公开(公告)日：1999-10-05
申请号：US964761
申请日：1997-11-05
申请人： Charles W. Forsberg
发明人： Charles W. Forsberg
IPC分类号： C03B5/00 , G21C19/46 , G21C19/48 , G21F9/30 , G21F9/00
CPC分类号： G21C19/46 , C03B5/005 , G21C19/48 , G21F9/305 , Y02P40/52 , Y02W30/883 , Y02W30/884
摘要： A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.
摘要翻译：从复杂的废料进料中回收诸如铀，钚和稀土元素等易裂变材料的方法，并将剩余的废物转化成适用于储存或处理的废玻璃。废料与由氧化铅和氧化硼形成的溶解玻璃混合，导致金属氧化物的氧化，脱卤和溶解。加入碳以除去氧化铅，生成氧化硼熔融熔融物。熔融熔体基本上没有有机物质和卤素，容易而迅速的溶解在硝酸中。溶解后，将铀，钚和稀土元素与酸分离，并通过PUREX或离子交换等工艺回收。剩余的酸性废物流被玻璃化以产生适于储存或处理的废玻璃。潜在的废物饲料包括钚废料和残留物，杂项废核燃料和铀裂变废物。初始进料可以包含金属，陶瓷，无定形固体，卤化物，有机材料和其它含碳材料的混合物。

9. 发明授权

US5461185A Radioactive waste material disposal 失效
标题翻译：放射性废物处理
公开(公告)号：US5461185A
公开(公告)日：1995-10-24
申请号：US230156
申请日：1994-04-19
申请人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
发明人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
IPC分类号： G21F9/30 , G21F9/34 , G21F9/00
CPC分类号： C03C1/002 , G21F9/305 , G21F9/34
摘要： The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.
摘要翻译：本发明是将固体放射性废物，特别是废核燃料及其包层（如果有的话）直接转化成固化的废玻璃的方法。溶解在玻璃浴中的牺牲金属氧化物用于氧化元素金属和废物中存在的任何碳值，因为它们被送入浴中。取决于所使用的牺牲金属氧化物，两种不同的操作模式是可能的。在第一模式中，使用可再生的牺牲氧化物，例如PbO，而第二模式特征在于使用诸如氧化铁的一次性氧化物。

10. 发明授权

US5410577A Core-melt source reduction system 失效
标题翻译：核心熔体源减少系统
公开(公告)号：US5410577A
公开(公告)日：1995-04-25
申请号：US147853
申请日：1993-11-04
申请人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
发明人： Charles W. Forsberg , Edward C. Beahm , George W. Parker
IPC分类号： G21C9/016
CPC分类号： G21C9/016 , G21Y2002/201 , G21Y2002/50 , G21Y2004/10 , G21Y2004/303 , Y02E30/40
摘要： A core-melt source reduction system for ending the progression of a molten core during a core-melt accident and resulting in a stable solid cool matrix. The system includes alternating layers of a core debris absorbing material and a barrier material. The core debris absorbing material serves to react with and absorb the molten core such that containment overpressurization and/or failure does not occur. The barrier material slows the progression of the molten core debris through the system such that the molten core has sufficient time to react with the core absorbing material. The system includes a provision for cooling the glass/molten core mass after the reaction such that a stable solid cool matrix results.
摘要翻译：一种芯熔体源还原系统，用于在芯熔事故期间结束熔芯的进展，并产生稳定的固体冷却基质。该系统包括核心碎片吸收材料和阻挡材料的交替层。核心碎屑吸收材料用于与熔核反应并吸收，使得不会发生容纳过压和/或失效。阻挡材料减慢熔融芯碎屑通过系统的进行，使得熔融芯具有足够的时间与芯吸收材料反应。该系统包括用于在反应之后冷却玻璃/熔核体的设备，使得得到稳定的固体冷却基质。

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