公开(公告)号：US5245644A

公开(公告)日：1993-09-14

申请号：US822336

申请日：1992-01-17

申请人： Martin Buttner ,  Josef Steven

发明人： Martin Buttner ,  Josef Steven

IPC分类号： G21C3/352

CPC分类号： G21C3/352 ,  Y02E30/40

摘要： A spacer for a fuel assembly of a pressurized water reactor includes a first group of first webs standing on end and extending parallel to one another in a plane. Each of the first webs has longer sides and shorter sides. One of the longer sides of each of the first webs has a slit formed therein with a narrowed point and an impressed indentation. A second group of second webs stand on end and extend at right angles to the first webs. Each of the second webs has longer sides and shorter sides. Another of the longer sides of each of the second webs has a slit formed therein with a narrowed point and an impressed indentation. Each respective one of the first webs is connected to a respective one of the second webs to form a grid by inserting the webs into each other at the slits and locking the narrowed point of one web into place in the impressed indentation of another web with a plug-in connection.

摘要翻译： 用于压水反应堆的燃料组件的间隔件包括第一组第一腹板，其位于端部并且平行于彼此平行延伸。 每个第一幅材具有较长的边和较短的边。 每个第一幅材的每个长边中的一个具有形成在其中的狭缝和凹陷的狭缝。 第二组第二网站的端部并且与第一腹板成直角地延伸。 每个第二腹板具有较长的侧面和较短的侧面。 每个第二幅材的另一个较长的侧面具有形成有狭缝和凹陷的狭缝的狭缝。 每个相应的一个第一腹板连接到相应的一个第二腹板以通过将腹板彼此插入狭缝处形成网格，并将一个腹板的狭窄点锁定在另一个腹板的压入凹陷中的位置，其中 插件连接。

公开(公告)号：US3940313A

公开(公告)日：1976-02-24

申请号：US418009

申请日：1973-11-21

申请人： Josef Steven

发明人： Josef Steven

IPC分类号： G01M3/04 ,  G21C17/07 ,  G21C3/16

CPC分类号： G21C17/07 ,  G01M3/045

摘要： A moisture sensor is provided for a nuclear fuel rod for water-cooled nuclear reactors wherein moisture can be present. The fuel rod has an end cap and a charge of nuclear fuel. The moisture sensor is disposed between the end cap and the charge and serves to detect a leak in the fuel rod. The moisture sensor includes a capsule-like housing having an inner space and having openings through which moisture can pass into the inner space in the event of a leak in the fuel rod. Ferromagnetic material is disposed in the inner space of the housing together with a moisture detector responsive to moisture for altering the disposition of the ferromagnetic material in the inner space.

摘要翻译： 为水冷核反应堆的核燃料棒提供湿气传感器，其中可以存在水分。 燃料棒具有端盖和核燃料。 水分传感器设置在端盖和充电之间，用于检测燃料棒中的泄漏。 水分传感器包括具有内部空间并具有开口的胶囊状壳体，在燃料棒中泄漏的情况下，水分可通过该开口进入内部空间。 铁磁材料与壳体的内部空间一起设置，并且响应于水分的湿度检测器改变内部空间中的铁磁材料的布置。

公开(公告)号：US5026517A

公开(公告)日：1991-06-25

申请号：US579241

申请日：1990-09-04

申请人： Gunther Menken ,  Hans-Jurgen Romeiser ,  Josef Steven

发明人： Gunther Menken ,  Hans-Jurgen Romeiser ,  Josef Steven

IPC分类号： G21C3/07

CPC分类号： G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/40 ,  Y10T428/294

摘要： A nuclear power plant has a water or liquid sodium coolant and a metallic component having surfaces coming into contact with the coolant. A coating is disposed on the surfaces of the metallic component, such as fuel rod cladding tubes or spacer grids. The coating is formed of titanium carbide (TiC), titanium nitride (TiN), zirconium nitride (ZrN), chromium carbide (CrC), titanium aluminum vanadium nitride (TiAlVN), tantalum nitride (TaN), zirconium carbide (ZrC), or tungsten carbide (WC).

摘要翻译： 核电站具有水或液态钠冷却剂和具有与冷却剂接触的表面的金属部件。 在金属部件的表面上设置涂层，例如燃料棒包覆管或间隔栅格。 涂层由碳化钛（TiC），氮化钛（TiN），氮化锆（ZrN），碳化铬（CrC），钛铝钒（TiAlVN），氮化钽（TaN），碳化锆（ZrC）或 碳化钨（WC）。

公开(公告)号：US4121972A

公开(公告)日：1978-10-24

申请号：US725197

申请日：1976-09-21

申请人： Josef Steven

发明人： Josef Steven

IPC分类号： G21C3/17 ,  G21C3/02

CPC分类号： G21C3/17 ,  Y02E30/40

摘要： A nuclear reactor fuel rod formed of a cladding tube, end caps hermetically sealing the tube at both ends thereof, the tube being divided transversely into two longitudinal zones one of which is for receiving a charge of nuclear fuel and the other of which is for receiving gas-adsorbing material free of nuclear fuel, includes means received in the second zone for simultaneously supporting the tube and for containing gas-adsorbing material therein, the means having a capsule having an open end facing toward the one zone and a gas-permeable member closing off the open end of the capsule, the capsule containing adsorber material that has been dried and degassed in high vacuum at temperatures of from 500.degree. to 1000.degree. C, the capsule having an interior space between the adsorber material contained therein and the gas-permeable element, and including a metallic foil destructible by a given internal pressure of the fuel rod gas-tightly closing the interior space; and method of production.

摘要翻译： 一种由包层管形成的核反应堆燃料棒，端盖在其两端气密地密封管，管被横向划分成两个纵向区，其中一个纵向区用于接收核燃料，另一个用于接收 不含核燃料的气体吸附材料包括接收在第二区域中以同时支撑管并用于在其中容纳气体吸附材料的装置，该装置具有开口端面向一个区域的气囊和透气构件 关闭胶囊的开口端，该胶囊含有已经在500-1000℃的高真空下被干燥和脱气的吸附材料，该胶囊在其中容纳的吸附材料和气 - 并且包括通过燃料棒的给定内部压力可破坏的金属箔，气密地封闭内部空间; 和生产方法。

公开(公告)号：US06320925B1

公开(公告)日：2001-11-20

申请号：US09238857

申请日：1999-01-27

申请人： Reiner Manzel ,  Werner Jahreiss ,  Norbert Schmidt ,  Josef Steven ,  Peter Dewes ,  Friedrich Garzarolli ,  Erhard Ortlieb ,  Franz-Josef Bökers ,  Matthias Rudolph

发明人： Reiner Manzel ,  Werner Jahreiss ,  Norbert Schmidt ,  Josef Steven ,  Peter Dewes ,  Friedrich Garzarolli ,  Erhard Ortlieb ,  Franz-Josef Bökers ,  Matthias Rudolph

IPC分类号： G21C3352

CPC分类号： G21C3/352 ,  G21C3/3424 ,  G21Y2002/103 ,  G21Y2004/301 ,  G21Y2004/305 ,  Y02E30/40

摘要： A spacer of a fuel assembly having intersecting webs undergoes reduced longitudinal expansion as a result of corrosion during an operating period. The webs have intersection locations at which assembly gaps are provided. The assembly gaps have widths which correspond essentially, at most over a fraction of their total length, to the wall thickness of an intersecting web, but are wider in a remaining region. Since corrosion layers growing from an edge of an assembly gap toward the intersecting web cannot touch the web, no solid pressure, which could lead to longitudinal expansion, builds up.

摘要翻译： 具有相交腹板的燃料组件的间隔件在操作期间由于腐蚀而经历减小的纵向膨胀。 腹板具有提供组装间隙的交叉位置。 组装间隙的宽度基本上相当于其总长度的一小部分，与相交网的壁厚度相对应，但在其余区域中较宽。 由于从组装间隙的边缘朝向相交的幅材生长的腐蚀层不能接触幅材，所以不会产生可能导致纵向膨胀的固体压力。

公开(公告)号：US4705663A

公开(公告)日：1987-11-10

申请号：US801140

申请日：1985-11-22

申请人： Josef Steven ,  Karl Hassfurther

发明人： Josef Steven ,  Karl Hassfurther

IPC分类号： G04G5/02 ,  G21C3/324 ,  G21C3/33 ,  G21C3/34

CPC分类号： G21C3/34 ,  G21C3/324 ,  G21C3/33 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/40

摘要： In a nuclear reactor fuel element for receiving mutually parallel rods, the improvement includes a rectangular grid-shaped spacer including planar webs crossing and facing the rods defining grid mesh openings receiving the rods, the webs including two outer webs forming an outer corner of the spacer and defining a corner grid mesh opening at the outer corner, the outer corner having an outward curve being curved in a direction parallel to the longitudinal direction of the rods, the outer webs having edges at the curve transverse to the rods being drawn inward toward the rods in the corner grid mesh opening forming a bevel in longitudinal direction of the rod.

摘要翻译： 在用于接收相互平行的杆的核反应堆燃料元件中，改进包括矩形格子状的间隔物，其包括平面的腹板，该平面腹板横过并且面向限定接纳杆的网格网孔的杆，该腹板包括形成间隔件的外角的两个外腹板 并且在外角处限定角格网格开口，外角具有在与杆的纵向方向平行的方向上弯曲的外侧曲线，具有横向于杆的弯曲边缘的外侧腹板朝向 角格栅网中的杆在杆的纵向方向上形成斜面。

公开(公告)号：US4246783A

公开(公告)日：1981-01-27

申请号：US957425

申请日：1978-11-02

申请人： Josef Steven ,  Helmut Bezold

发明人： Josef Steven ,  Helmut Bezold

IPC分类号： G01L1/22 ,  G01L5/00 ,  G01L5/10 ,  G21C3/356 ,  G21C17/06 ,  G21C19/00 ,  G01M19/00

CPC分类号： G01L5/106 ,  G01L1/22 ,  G01L5/0057 ,  G01L5/10 ,  G21C3/3563 ,  Y02E30/40

摘要： Device for measuring the spring-force of resilient spacer projections set into spacer grids of nuclear reactor fuel assemblies to push fuel rods surrounded by spacer meshes against at least two oppositely disposed rigid spacer projections, including a force measuring plug having a diameter equal to the diameter of a fuel rod to be fixed in the spacer grid, and a flexible beam integral with the force measuring plug, the flexible beam having a free end in contact with a first resilient spacer projection to be measured, and another end firmly connected to the force measuring plug and having at least one wire strain gage disposed thereon.

摘要翻译： 用于测量设置在核反应堆燃料组件的间隔栅格中的弹性间隔物突起的弹簧力的装置，用于将由间隔物网围绕的燃料棒推向至少两个相对设置的刚性间隔件突出部，包括直径等于直径的力测量塞 固定在隔离栅格中的燃料棒以及与力测量插塞成一体的柔性梁，该柔性梁具有与待测量的第一弹性间隔件突起接触的自由端，以及牢固地连接到该力的另一端 测量插头并且具有布置在其上的至少一个线应变计。

公开(公告)号：US3997394A

公开(公告)日：1976-12-14

申请号：US560387

申请日：1975-03-20

申请人： Friedrich-Wilhelm Aisch ,  Hans Peter Fuchs ,  Diethelm Knodler ,  Alexander Steinke ,  Josef Steven

发明人： Friedrich-Wilhelm Aisch ,  Hans Peter Fuchs ,  Diethelm Knodler ,  Alexander Steinke ,  Josef Steven

IPC分类号： G21C3/326 ,  G21C3/33 ,  G21C9/00 ,  G21C3/30

CPC分类号： G21C3/3305 ,  G21C3/326 ,  G21C3/3315 ,  G21C9/00 ,  Y02E30/32 ,  Y02E30/38

摘要： For use in forming the core of a pressurized-water reactor, a fuel assembly supporting structure for holding a bundle of interspaced fuel rods, is formed by interspaced end pieces having holes in which the end portions of control rod guide tubes are inserted, fuel rod spacer grids being positioned by these guide tubes between the end pieces. The end pieces are fastened to the end portions of the guide tubes, to integrate the supporting structure, and in the case of at least one of the end pieces, this is done by means which releases that end piece from the guide tubes when the end pieces receive an abnormal thrust force directed towards each other and which would otherwise place the guide tubes under a compressive stress that would cause them to buckle. The spacer grids normally hold the fuel rods interspaced by distances determined by nuclear physics, and buckling of the control rod guide tubes can distort the fuel rod spacer grids with consequent dearrangement of the fuel rod interspacing. A sudden loss of pressure in a pressurized-water reactor pressure vessel, can result in the pressurized coolant in the vessel, discharging from the vessel at such high velocity as to result in the abnormal thrust force on the end pieces of each fuel assembly, which could cause buckling of the control rod guide tubes when the end pieces are fixed to them in the normal rigid and unyielding manner.

摘要翻译： 为了用于形成加压水反应堆的核心，用于保持一束间隔燃料棒的燃料组件支撑结构由具有孔的间隔端部件形成，控制杆导管的端部插入孔中，燃料棒 间隔网格由这些引导管定位在端部件之间。 端部件紧固到导管的端部，以将支撑结构集成在一起，并且在至少一个端部件的情况下，这是通过将端部件从导管释放的装置来完成的，当端部 部件接收到彼此指向的异常推力，否则将引导管放置在会导致其弯曲的压缩应力下。 间隔栅格通常保持燃料棒间隔由核物理学确定的距离，并且控制杆导管的弯曲可以使燃料棒间隔栅格变形，从而导致燃料棒间隔的分离。 压力水反应堆压力容器中突然的压力损失可能导致容器中的加压冷却剂以高速度从容器排出，从而导致每个燃料组件的端部件上的异常推力， 当端板以正常的刚性和不屈服的方式固定到它们时，可能导致控制杆导管的翘曲。