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1. 发明授权

US4661312A Pressure relief system in nuclear reactors 失效
标题翻译：核反应堆压力释放系统
公开(公告)号：US4661312A
公开(公告)日：1987-04-28
申请号：US628140
申请日：1984-07-10
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： G21C9/00 , G21C9/004 , G21C19/20
CPC分类号： G21C9/004 , Y02E30/40
摘要： A nuclear reactor, particularly a light water reactor or a helium-cooled high-temperature reactor, is provided with a pressure relief system for relieving pressure resulting under fault conditions from coolant in the reactor pressure vessel and/or the protective vessel of the reactor, wherein the coolant is conducted from the vessel or vessels to a pressure relief station downstream thereof. At the pressure relief station the coolant is fed into a liquid reservoir 4 from which the coolant in gaseous or vapor form is fed sequentially through a washing cyclone 13 and a drying cyclone 25. Most of the radioactive fission products carried by the coolant will have been removed by the liquid reservoir 4 and the washing cyclone 13, and the coolant leaving the cyclone 25 may be safely discharged to atmosphere. Both the liquid reservoir 4 and the washing cyclone 13 are provided with cooling circuits 8 to 12 and 14 to 23 respectively for the liquids.
摘要翻译：核反应堆，特别是轻水反应器或氦冷却的高温反应器设置有用于在故障条件下从压力容器和/或反应堆的保护容器中的冷却剂释放压力的压力释放系统，其中所述冷却剂从所述容器或容器传导到其下游的压力释放站。在减压站，冷却剂被送入液体储存器4，气体或蒸气形式的冷却剂从该储存器顺序地通过洗涤旋流器13和干燥旋风分离器25进料。大部分由冷却剂携带的放射性裂变产物将被通过液体贮存器4和洗涤旋流器13移除，并且离开旋风分离器25的冷却剂可以被安全地排放到大气中。液体贮存器4和洗涤旋流器13分别为液体设置有冷却回路8至12和14至23。

2. 发明授权

US4243487A Gas-cooled high temperature nuclear reactors 失效
标题翻译：气冷式高温核反应堆
公开(公告)号：US4243487A
公开(公告)日：1981-01-06
申请号：US899970
申请日：1978-04-25
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： G21C15/02 , F22B1/18 , G21C1/07 , G21C11/06 , G21C13/00 , G21C15/26 , G21C9/00
CPC分类号： G21C15/26 , F22B1/1823 , G21C1/07 , G21C11/06 , Y02E30/33 , Y02E30/36
摘要： A gas-cooled, and preferably helium cooled, graphite-moderated high temperature nuclear reactor of the kind having a pressure vessel containing a reactor core with fuel elements, graphite components and a primary coolant gas circuit including a steam generator and coolant gas blowers, has the steam generator disposed outside the pressure vessel and the steam generator includes a heat exchanger at least a portion of which is located above the level of the reactor core. This situation of the heat exchanger ensures that when the reactor is shut down, either intentionally or owing to a fault, a natural convection flow takes place through the coolant gas circuit and this natural convection flow is in the same direction as it is when the blowers are functioning so that the flow conducts away the decay heat from the core to the steam generator in the same way as when the blowers are in operation.
摘要翻译：具有包含具有燃料元件，石墨部件和包括蒸汽发生器和冷却剂气体鼓风机的主要冷却剂气体回路的反应堆芯的压力容器的气冷的，优选氦冷却的石墨缓和的高温核反应堆具有设置在压力容器外部的蒸汽发生器和蒸汽发生器包括其至少一部分位于反应堆堆芯的水平面之上的热交换器。热交换器的这种情况确保了当反应器有意或由于故障而关闭时，通过冷却剂气体回路发生自然对流，并且该自然对流与鼓风机的方向相同以使得流体以与鼓风机运行时相同的方式将芯体的衰变热量传导到蒸汽发生器。

3. 发明授权

US4199405A Side reflector for a high-temperature nuclear reactor 失效
标题翻译：用于高温核反应堆的侧反射器
公开(公告)号：US4199405A
公开(公告)日：1980-04-22
申请号：US817741
申请日：1977-07-21
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： G21C1/12 , G21C11/06 , G21C5/08
CPC分类号： G21C11/06 , Y02E30/40
摘要： The invention relates to a graphite side reflector in block form for a gas-cooled high-temperature nuclear reactor. The blocks of the reflector extend radially continuously through the entire reflector wall thickness and recesses are provided in the inner end faces of at least the blocks disposed in the upper region of the reactor core.
摘要翻译：本发明涉及一种用于气体冷却的高温核反应堆的块状石墨侧反射器。反射器的块沿径向连续延伸穿过整个反射器壁厚度，并且至少设置在反应堆芯的上部区域中的块的内端面中设置凹部。

4. 发明授权

US4092217A Fuel elements for nuclear reactors and method for testing the circulation of fuel elements in a core of a nuclear reactor 失效
标题翻译：用于核反应堆的燃料元件和用于测试核反应堆核心中的燃料元件的循环的方法
公开(公告)号：US4092217A
公开(公告)日：1978-05-30
申请号：US455532
申请日：1974-03-28
申请人： Fritz Schweiger , Wilfried Fritzsche
发明人： Fritz Schweiger , Wilfried Fritzsche
IPC分类号： G01F1/708 , G01P5/20 , G01V3/10 , G01V3/11 , G21C17/00 , G21C17/06 , G21C3/00
CPC分类号： G21C17/066
摘要： A method of testing the circulation of a bulk charge of fuel elements in the core of a pebble bed type of nuclear reactor comprises increasing the electrical conductivity of a number of fuel elements and then injecting the marked elements into a bulk charge of other unmarked elements having a lower electrical conductivity at predetermined positions in the core of a nuclear reactor and a measured times. The marked fuel elements are subsequently detected electromagnetically as they are carried in the bulk charge of unmarked elements through an electromagnetic field generated by a detection and measurement station. The elements are marked by including a material having a greater electrical conductivity than the remainder of the element and this material may be coated on the surface of the elements or incorporated in the body of the elements.
摘要翻译：在卵石床型核反应堆的核心中测试燃料元件的大量电荷的循环的方法包括增加多个燃料元件的导电性，然后将标记的元件注入其他未标记元件的大量电荷中，在核反应堆的核心中的预定位置处的电导率低，并且测量时间。标记的燃料元件随后通过由检测和测量站产生的电磁场以非标记元件的大量电荷携带而被电磁检测。这些元件通过包括具有比元件的其余部分更大的导电性的材料来标记，并且该材料可以涂覆在元件的表面上或并入元件的主体中。

5. 发明授权

US4113559A Method of removing the decay heat of radioactive fission products 失效
标题翻译：消除放射性离子产物的衰变热的方法
公开(公告)号：US4113559A
公开(公告)日：1978-09-12
申请号：US674483
申请日：1976-04-07
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： G21C15/18 , G21C9/00
CPC分类号： G21C15/18 , Y02E30/33
摘要： A method of removing the decay heat of radioactive fission products from a gas-cooled high temperature nuclear reactor in an emergency situation wherein a fault or a combination of faults results in the normal operational systems of the reactor not being able to remove the decay heat satisfactorily, comprises introducing water into the reactor core. Preferably the water is completely desalinated water which is introduced into the core from above. Absorber material may also be mixed with the water before it is introduced into the core to effect permanent shutdown of the reactor by absorbing free neutrons within the core.

6. 发明授权

US4167444A Removal of impurities from the coolant gas of gas-cooled high temperature nuclear reactors 失效
标题翻译：从气体冷却高温核反应堆的冷却剂气体中除去杂质
公开(公告)号：US4167444A
公开(公告)日：1979-09-11
申请号：US750689
申请日：1976-12-15
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： B01D53/10 , G21C19/303 , G21D5/06 , G21C9/00
CPC分类号： G21C19/303
摘要： The coolant gas of a gas-cooled high temperature nuclear reactor, structu components or the fuel elements of which are made predominantly of graphite, is circulated through a coolant circuit of the reactor and through a gas purification plant, and to further remove impurities from the coolant gas, carbon dust of colloidal particle size is fed into the coolant gas preferably on its passage back from the purification plant into the coolant circuit. The carbon dust may be monoatomic carbon or activated carbon, coke, carbon black or a mixture thereof. Preferably the coolant gas of the reactor is charged with the carbon dust before the reactor is initially started up and hot-run and the coolant gas charged with the carbon dust is circulated for a sufficiently long period to coat all metal surfaces in the coolant circuit with carbon dust before the initial starting up and hot-running takes place.
摘要翻译：气体冷却的高温核反应堆的冷却剂气体，结构部件或其燃料元素主要由石墨制成，通过反应器的冷却剂回路并通过气体净化设备循环，并进一步从冷却剂气体，胶体粒度的碳粉末优选地在冷却剂气体从净化设备返回到冷却剂回路中的同时被送入冷却剂气体。碳粉可以是单原子碳或活性炭，焦炭，炭黑或其混合物。优选地，反应器的冷却剂气体在反应器最初启动和热运行之前被填充碳粉，并且充满碳尘的冷却剂气体循环足够长的时间以涂覆冷却剂回路中的所有金属表面，在初始启动和热运行之前，碳粉尘发生。

7. 发明授权

US3979258A Nuclear reactor 失效
标题翻译：核反应堆
公开(公告)号：US3979258A
公开(公告)日：1976-09-07
申请号：US456850
申请日：1974-04-01
申请人： Fritz Schweiger , Erwin Glahe
发明人： Fritz Schweiger , Erwin Glahe
IPC分类号： G21C7/107 , G21C7/10
CPC分类号： G21C7/107 , G21Y2002/303 , G21Y2004/30 , Y02E30/39
摘要： In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread.
摘要翻译：在装有球形反应元件的那种核反应堆中，其中控制棒布置成直接推入电荷中，每个控制棒在其外表面上具有至少一个螺纹，使得当杆被推入导致电荷旋转，从而使渗透更容易。每个控制杆的长度可以具有两个不同的部分，后者部分承载螺纹和导入部分，该部分比后者部分短，并且可以承载比后者部分螺距更大的螺纹，或者可以具有多个轴向延伸的肋而不是螺纹。

8. 发明授权

US4816209A Method and apparatus for separating radioactive constituents from gas or vapors escaping accidentally from nuclear reactors 失效
标题翻译：将放射性成分与从核反应堆意外逃逸的气体或蒸气分离的方法和装置
公开(公告)号：US4816209A
公开(公告)日：1989-03-28
申请号：US890834
申请日：1986-07-25
申请人： Fritz Schweiger
发明人： Fritz Schweiger
IPC分类号： G21F9/02 , B01D59/00 , G21C19/303 , G21F9/00 , G21C9/00 , B01D47/02
CPC分类号： G21C19/303 , Y10S55/09
摘要： To separate tritium from gases and/or vapors escaping accidentally from a clear reactor, before the gases or vapor are discharged into the atmosphere, the gases or vapor are fed through a line 5 into a reservoir 3 of deionized light water which is maintained at its boiling point in a heat insulated vessel 1. The tritium is accumulated in the water in the reservoir 3 and any tritium which passes from the reservoir 3 in light water steam is condensed by surface condensors 8 in a steam dome 9. Any possible residue of tritium in the steam leaving through an outlet 10 at the top of the dome 9 is separated out in the form of droplets by a drier cyclone connected directly downstream of the outlet 10.
摘要翻译：为了将氚与来自核反应堆的意外泄漏的气体和/或蒸汽分离，在气体或蒸气排放到大气中之前，气体或蒸汽通过管线5进入到保持在其中的去离子水的储存器3中在隔热容器1中的沸点。氚积聚在储存器3中的水中，并且在轻水蒸气中从储存器3通过的任何氚在蒸汽穹顶9中被表面冷凝器8冷凝。任何可能的氚残留物在通过圆顶9的顶部处的出口10离开的蒸汽通过直接在出口10的下游连接的干燥旋风分离器以液滴的形式分离。

9. 发明授权

US4486380A Method of shutting down a high-temperature reactor 失效
标题翻译：关闭高温反应堆的方法
公开(公告)号：US4486380A
公开(公告)日：1984-12-04
申请号：US286160
申请日：1981-07-23
申请人： Fritz Schweiger , Jurgen Wohler
发明人： Fritz Schweiger , Jurgen Wohler
IPC分类号： G21C7/00 , G21C7/02 , G21C7/32
CPC分类号： G21C7/32 , G21C7/00 , G21Y2002/202 , G21Y2004/302 , G21Y2004/40 , Y02E30/33 , Y02E30/36 , Y02E30/39
摘要： In the method of shutting down a high temperature nuclear reactor having a negative temperature coefficient of reactivity, such as a gas cooled pebble-bed nuclear reactor, while the core is operating in the critical state with the core having a predetermined critical average core temperature and with the heat generated in the critical state being removed by a coolant, effecting the shut down by reducing or discontinuing the removal of heat from the reactor core and increasing the average core temperature by an amount above the critical average core temperature for rendering the core hot sub-critical due to the negative temperature coefficient of reactivity. The core can be maintained in the hot sub-critical state by a controlled removal of after shut-down heat from the core.
摘要翻译：在关闭具有负温度反应温度系数的高温核反应堆的方法中，例如气体冷却的卵石床核反应堆，同时核心以核心具有预定临界平均核心温度运行在临界状态，而在临界状态下产生的热量被冷却剂除去，通过减少或停止从反应堆堆芯中除去热量并使平均炉芯温度升高高于临界平均炉芯温度，从而使炉芯变热由于反应性的负温度系数，亚临界。核心可以通过从核心关闭热量后的受控去除而保持在热的亚临界状态。

10. 发明授权

US3971444A Reaction vessels charged with spherical elements 失效
标题翻译：装有球形元件的反应容器
公开(公告)号：US3971444A
公开(公告)日：1976-07-27
申请号：US490692
申请日：1974-07-22
申请人： Fritz Schweiger , Jurgen Wohler
发明人： Fritz Schweiger , Jurgen Wohler
IPC分类号： G21C1/07 , G21C19/00
CPC分类号： G21C1/07 , Y02E30/36
摘要： A reaction vessel which holds a charge of spherical reaction elements, for example a pebble bed nuclear reactor having a charge of spherical fuel elements, has the charge formed of at least two groups of spherical elements with all of the elements in each group being of equal diameter, but each group of elements having a different diameter from the other. The elements of both groups are uniformly mixed together and the different diameters are chosen in such a way that when the elements are continuously circulated through the reaction vessel during operation, the circulation does not cause the two groups of elements to segregate during the intended number of circulation cycles. Further, when control rods are used in a nuclear reactor which are advanced into and retracted from direct contact with the spherical elements for providing control and shutdown of the nuclear reaction, the use of spherical elements selected from at least two groups, each of which has a different diameter and where the difference in diameters is in a selected range so that the random arrangement of elements is maintained during continuous circulation of the core, prevents the elements from becoming tightly packed together so that insertion of the control rods into the core is facilitated.
摘要翻译：保持球形反应元件的反应容器，例如具有球形燃料元件电荷的卵石床核反应堆，具有由至少两组球形元素形成的电荷，每组中的所有元素均等但是每组元件具有与另一直径不同的直径。两组元件均匀地混合在一起，并且以这样的方式选择不同的直径：当元件在操作期间连续循环通过反应容器时，循环不会导致两组元件在预期数量循环周期。此外，当将控制棒用于前进到与球形元件直接接触并用于提供核反应的关闭的球形元件缩回的核反应堆时，使用选自至少两个组的球形元件，每个组具有直径不同且直径差在选定范围内，使得在芯的连续循环期间元件的随机布置得以保持，防止元件紧密地包装在一起，从而便于将控制棒插入到芯体中。

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