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1.发明授权Matrix material comprising graphite and an inorganic binder suited for final disposal of radioactive waste, a process for producing the same and its processing and use 有权包含石墨和适用于最终处置放射性废物的无机粘合剂的基质材料，其制备方法及其加工和用途公开(公告)号：US08502009B2
公开(公告)日：2013-08-06
申请号：US12626721
申请日：2009-11-27
申请人： Milan Hrovat , Karl-Heinz Grosse , Richard Seemann
发明人： Milan Hrovat , Karl-Heinz Grosse , Richard Seemann
CPC分类号： C03C14/00 , C03C2214/14 , G21F9/302 , G21F9/305 , G21F9/36
摘要： A matrix material for safe temporary and/or ultimate disposal of radioactive wastes suitable for the embedment of radioactive wastes, contains graphite and at least inorganic binder which can be glass, aluminosilicate, silicate, borate and lead sulfide.
摘要翻译： 用于安全临时和/或最终处置适用于放射性废物包埋的放射性废物的基质材料包含石墨和至少无机粘合剂，其可以是玻璃，硅铝酸盐，硅酸盐，硼酸盐和硫化铅。
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公开(公告)号：US20130012374A1
公开(公告)日：2013-01-10
申请号：US13637077
申请日：2011-03-24
申请人： Milan Hrovat , Richard Seemann , Karl-Heinz Grosse
发明人： Milan Hrovat , Richard Seemann , Karl-Heinz Grosse
摘要： A package for storing radioactive waste, which is suitable for safe, ultra-long ultimate disposal having a moisture-impermeable, corrosion-resistant graphite matrix and metal-encased waste products, which are embedded into the matrix. A method for producing such packages is also part of the invention.
摘要翻译： 一种用于储存放射性废物的包装，适用于安全，超长的最终处理，具有不透水，耐腐蚀的石墨基质和金属包裹的废物，嵌入基质中。 制造这种包装的方法也是本发明的一部分。
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3.发明申请REFLECTOR GRAPHITE CONSISTING OF ISOTROPIC HIGHLY CRYSTALLINE NATURAL GRAPHITE AS THE MAIN COMPONENT AND SILICON OR ZIRCONIUM CARBIDE, AND PRODUCTION THEREOF 审中-公开主要成分为高分子自然石墨作为主要组分和硅或碳化硅的反射石墨及其生产公开(公告)号：US20100294995A1
公开(公告)日：2010-11-25
申请号：US12743685
申请日：2008-11-19
申请人： Milan Hrovat , Karl-Heinz Grosse , Richard Seemann
发明人： Milan Hrovat , Karl-Heinz Grosse , Richard Seemann
CPC分类号： C04B35/522 , C04B35/532 , C04B35/632 , C04B2235/3244 , C04B2235/3418 , C04B2235/3826 , C04B2235/3839 , C04B2235/424 , C04B2235/5409 , C04B2235/5436 , C04B2235/5445 , C04B2235/604 , C04B2235/608 , C04B2235/6581 , C04B2235/77 , C04B2235/80 , C04B2235/94 , C04B2235/95 , C04B2235/96 , C04B2235/9607 , C04B2235/9684 , G21C5/126 , G21C11/06 , Y02E30/40
摘要： Disclosed is reflector graphic which is characterized in that the main component of the graphite is nuclear-purity natural graphite in addition to silicon carbide and/or zirconium carbide, the pressed pieces are shaped by a combined cold-hot pressing process, and the thermal treatment of the pressed pieces is limited to temperatures of less than 2000° C.
摘要翻译： 公开了一种反射器图形，其特征在于除了碳化硅和/或碳化锆之外，石墨的主要成分是核纯天然石墨，压制片通过组合冷热压成型，热处理 的压制件被限制在低于2000℃的温度
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4.发明申请SPHERICAL FUEL ELEMENT AND PRODUCTION THEREOF FOR GAS-COOLED HIGH TEMPERATURE PEBBLE BED NUCLEAR REACTORS (HTR) 失效气体燃料元件及其生产用于气体冷却的高温PEBBLE核反应堆（HTR）公开(公告)号：US20100014625A1
公开(公告)日：2010-01-21
申请号：US12439203
申请日：2007-08-28
申请人： Milan Hrovat , Karl-Heinz Grosse , Rainer Schulten
发明人： Milan Hrovat , Karl-Heinz Grosse , Rainer Schulten
CPC分类号： G21C3/04 , G21C21/00 , G21Y2002/103 , G21Y2002/104 , G21Y2002/303 , G21Y2004/10 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： The invention relates to a novel design and production of fuel element pebbles which satisfy the requirements of high temperature pebble bed nuclear reactors of the next generation. The invention uses a shell of the fuel element pebbles that is devoid of fuel and consists of silicon carbide (SiC) and/or zircon carbide (ZrC), in addition to natural graphite and graphitized petroleum coke, said shell having a maximum average nominal thickness of 5 mm and preferably only 3 mm.
摘要翻译： 本发明涉及满足下一代高温卵石床核反应堆要求的燃料元件鹅卵石的新颖设计和生产。 本发明除了天然石墨和石墨化石油焦之外还使用不含燃料并由碳化硅（SiC）和/或锆石碳化物（ZrC）组成的燃料元件鹅卵石壳，所述外壳具有最大平均标称厚度 为5毫米，最好只有3毫米。
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5.发明授权Spherical fuel element and production thereof for gas-cooled high temperature pebble bed nuclear reactors (HTR) 失效球形燃料元件及其制备用于气冷高温卵石床核反应堆（HTR）公开(公告)号：US08243871B2
公开(公告)日：2012-08-14
申请号：US12439203
申请日：2007-08-28
申请人： Milan Hrovat , Karl-Heinz Grosse , Rainer Schulten
发明人： Milan Hrovat , Karl-Heinz Grosse , Rainer Schulten
IPC分类号： G21C19/28
CPC分类号： G21C3/04 , G21C21/00 , G21Y2002/103 , G21Y2002/104 , G21Y2002/303 , G21Y2004/10 , G21Y2004/30 , G21Y2004/40 , Y02E30/40
摘要： The invention relates to a novel design and production of fuel element pebbles which satisfy the requirements of high temperature pebble bed nuclear reactors of the next generation. The invention uses a shell of the fuel element pebbles that is devoid of fuel and consists of silicon carbide (SiC) and/or zircon carbide (ZrC), in addition to natural graphite and graphitized petroleum coke, said shell having a maximum average nominal thickness of 5 mm and preferably only 3 mm.
摘要翻译： 本发明涉及满足下一代高温卵石床核反应堆要求的燃料元件鹅卵石的新颖设计和生产。 本发明除了天然石墨和石墨化石油焦之外还使用不含燃料并由碳化硅（SiC）和/或锆石碳化物（ZrC）组成的燃料元件鹅卵石壳，所述外壳具有最大平均标称厚度 为5毫米，最好只有3毫米。
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公开(公告)号：US5489422A
公开(公告)日：1996-02-06
申请号：US302736
申请日：1994-09-09
IPC分类号： C04B41/87 , C04B41/52 , C04B41/89 , C23C16/34 , C23C16/50 , C23C16/511 , C23C28/04 , D01F9/12
CPC分类号： C04B41/89 , C04B41/526 , C23C16/345 , C23C16/511 , C23C28/044 , C23C28/046 , Y10S428/902 , Y10T29/4927 , Y10T29/49272 , Y10T428/30
摘要： In order to have carbon fiber reinforced carbon resistant to oxidation, the proposal is for a process by means of which a bonding layer of amorphous SiNx is applied to the carbon fiber reinforced carbon to which in turn is applied a protective layer which is oxidation resistant at a temperature T, where T>400.degree. C. consisting preferably of Si.sub.3 N.sub.4.
摘要翻译： PCT No.PCT / EP93 / 00508 Sec。 371日期1994年9月9日 102（e）1994年9月9日PCT 1993年3月6日PCT公布。 公开号WO93 / 18203 日本1993年9月16日。为了使碳纤维增强的碳抗氧化，提出了一种方法，通过该方法将非晶SiNx的结合层施加到碳纤维增强碳上，再加上碳 在温度T下，其中T> 400℃，优选由Si 3 N 4组成的抗氧化保护层。
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7.发明授权Spherical fuel elements made of graphite for temperature reactors and process for reworking it after the irradiation 失效用于温度反应器的由石墨制成的球形燃料元件，以及在照射后对其进行再加工的工艺
公开(公告)号：US4134941A
公开(公告)日：1979-01-16
申请号：US753098
申请日：1976-12-21
申请人： Milan Hrovat , Hans-Joachim Becker , Hans Huschka
发明人： Milan Hrovat , Hans-Joachim Becker , Hans Huschka
CPC分类号： G21C19/48 , G21C3/28 , Y02E30/40 , Y02W30/884
摘要： There are provided pressed spherical fuel elements for high temperature reactors made of a graphite matrix with separate embedded coated fuel and fertile material particles wherein the fuel elements comprise 3 concentric layers including a graphite nucleus or core (1) which only contains fertile material particles (4), this graphite nucleus (1) is surrounded by a graphite zone (2) which only contains the fuel particles (5) and this is encased in a shell (3) of pure graphite, the same graphite material being present in all three layers.
摘要翻译： 提供了用石墨基质制成的高温反应器的压制球形燃料元件，其具有单独的嵌入式涂覆燃料和可育材料颗粒，其中燃料元件包括3个同心层，包括仅含有可育材料颗粒的石墨核或核（1） ），该石墨核（1）被只包含燃料颗粒（5）的石墨区（2）包围，并被包裹在纯石墨的壳（3）中，相同的石墨材料存在于所有三层中 。
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公开(公告)号：US4919867A
公开(公告)日：1990-04-24
申请号：US118035
申请日：1987-11-09
申请人： Wilhelm Konigs , Milan Hrovat
发明人： Wilhelm Konigs , Milan Hrovat
摘要： A method and a device for sintering ceramic shaped articles in a furnace which saves costs and energy but provides high throughput. To this end, the shaped articles are guided vertically through the furnace on the helical rib of a stationary, vertically positioned helix by the inner longitudinal ribs of a rotating, vertically standing tube which concentrically surrounds the helix.
摘要翻译： 一种用于在炉中烧结陶瓷成形制品的方法和装置，其节省成本和能量，但是提供高产量。 为此，成形制品通过同心地围绕螺旋的旋转的竖直立管的内部纵向肋垂直地引导通过固定的垂直定位的螺旋的螺旋肋上的炉子。
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公开(公告)号：US4407742A
公开(公告)日：1983-10-04
申请号：US143941
申请日：1980-04-25
申请人： Milan Hrovat , Hans Huschka , Lothar Rachor
发明人： Milan Hrovat , Hans Huschka , Lothar Rachor
CPC分类号： G21F9/34
摘要： Previously the conditioning of radioactive wastes took place through binding the waste in a matrix of glass, silicon carbide, cement, bitumen, synthetic resin or vitreous carbon. These processes have many disadvantages, particularly the matrix has poor heat conductivity, insufficient resistant to extraction or poor heat resistance and radiolysis effects. A remedy is provided through a carbon matrix in which there is employed as the starting material graphite which is molded with a binder at a temperature above 100.degree. C. There have particularly proven good as the binder sulfur in admixture with nickel powder from which nickel sulfide forms.
摘要翻译： 以前，放射性废物的调节是通过将废物与玻璃，碳化硅，水泥，沥青，合成树脂或玻璃碳的基体结合在一起的。 这些方法具有许多缺点，特别是基质的导热性差，耐萃取性能差，耐热性差，辐射效果好。 通过碳基质提供补救措施，其中使用作为起始材料的石墨，其在高于100℃的温度下用粘合剂模制。作为与镍粉混合的粘合剂硫已经被证明是好的，其中硫化镍 形式。
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10.发明授权Process for the production of pressed block fuel elements of high power for gas cooled high temperature reactor 失效用于生产用于气体冷却高温反应堆的大功率压块燃料元件的方法
公开(公告)号：US3996319A
公开(公告)日：1976-12-07
申请号：US486773
申请日：1974-07-09
CPC分类号： G21C3/28 , B30B11/04 , G21C21/02 , Y02E30/40 , Y10S376/903
摘要： Molded or pressed block fuel elements of high power for gas cooled high temperatures are produced by molding in steel tools using outer dies or bars and punches arranged to be freely moveable in the axial direction and moving said moveable dies or bars and punches in the molding process.
摘要翻译： 用于气体冷却高温的高功率成型或压制块燃料元件通过使用外模或棒的钢工具进行成型而制造，冲头布置成在轴向方向上可自由移动并且在成型过程中移动所述可移动模具或棒和冲头 。
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