SHIELDING FACILITY FOR X-RAYS OR 'gamma'-RAYS
    271.
    发明申请
    SHIELDING FACILITY FOR X-RAYS OR 'gamma'-RAYS 审中-公开
    X射线或伽马射线的屏蔽设备

    公开(公告)号:WO1997034305A1

    公开(公告)日:1997-09-18

    申请号:PCT/JP1997000772

    申请日:1997-03-12

    Abstract: A shielding facility serves to prevent x-rays or gamma -rays which are generated by, for example, irradiation of electron beam from leaking out of an opening through a shield passage. The shielding facility includes a shielding wall (2) defining therein a shield passage (3) having an inlet opening and an outlet opening. The shielding wall (2) is adapted to accommodate a source (1) which generates x-rays or gamma -rays. The shielding facility further includes a plurality of partition walls (7-1, 7-2 and 7-3) disposed in the shield passage (3). The partition walls (7-1, 7-2 and 7-3) are bent at least one time between the inlet opening and the outlet opening of the shield passage (3).

    Abstract translation: 屏蔽设备用于防止例如通过屏蔽通道从开口泄漏电子束的照射而产生的X射线或γ射线。 屏蔽设备包括屏蔽壁(2),其中限定有具有入口和出口的屏蔽通道(3)。 屏蔽壁(2)适于容纳产生x射线或γ射线的源(1)。 屏蔽设备还包括设置在屏蔽通道(3)中的多个分隔壁(7-1,7-2和7-3)。 分隔壁(7-1,7-2和7-3)在屏蔽通道(3)的入口和出口之间至少一次弯曲。

    NUCLEAR FUEL ASSEMBLY HAVING A TRANSITION PIECE WITH REDUCED FLOW RESISTANCE
    272.
    发明申请
    NUCLEAR FUEL ASSEMBLY HAVING A TRANSITION PIECE WITH REDUCED FLOW RESISTANCE 审中-公开
    具有降低流动阻力的过渡段的核燃料组件

    公开(公告)号:WO1997028535A1

    公开(公告)日:1997-08-07

    申请号:PCT/US1996001275

    申请日:1996-02-02

    Abstract: In order to reduce the flow resistance of a coolant flowing through a passage (63) in the support plate (64) of a boiling water reactor and entering the transition piece (50) at the lower end of a fuel assembly resting on said support plate (64), the lower rim (60) of the transition piece (50) forms a conically tapered surface which fits into a corresponding conical counter-surface (62) at the upper edge of said passage (63). The lower rim (60) of the transition piece (50) forms a circular inlet which is concentric with the passage (63) and has a size equal or slightly larger than the passage opening. Fingers (70) protruding laterally into said opening and extending down into said passage (63) are used to center the low rim (60) within the passage (63). Additionally, the end caps (90) of the fuel rods may be stream-lined and the lower tie plate (53) of the fuel assembly may be spaced apart from the inner surface of a fuel channel (52) by a plurality of ribs (86) which form a plurality of peripheral through holes (86') on each of the four inner surfaces (84) of the rectangular fuel channel (52).

    Abstract translation: 为了降低流过沸水反应堆的支撑板(64)中的通道(63)的冷却剂的流动阻力,并进入位于所述支撑板上的燃料组件的下端的过渡件(50) (64)中,过渡件(50)的下边缘(60)形成锥形锥形表面,该锥形表面装配在所述通道(63)的上边缘处的对应锥形对置表面(62)中。 过渡件(50)的下边缘(60)形成与通道(63)同心的圆形入口,其尺寸等于或稍大于通道开口。 用于将侧边突出到所述开口并向下延伸到所述通道(63)中的手指70将所述低边缘(60)定位在所述通道(63)内。 另外,燃料棒的端盖(90)可以是流线型的,并且燃料组件的下连接板(53)可以通过多个肋(...)与燃料通道(52)的内表面间隔开 86),其在矩形燃料通道(52)的四个内表面(84)中的每一个上形成多个周边通孔(86')。

    NUCLEAR FUEL ASSEMBLY WITH AN UPPER CAP
    273.
    发明申请
    NUCLEAR FUEL ASSEMBLY WITH AN UPPER CAP 审中-公开
    核燃料组件与上盖

    公开(公告)号:WO1997028534A1

    公开(公告)日:1997-08-07

    申请号:PCT/FR1997000212

    申请日:1997-02-03

    Inventor: FRAMATOME COGEMA

    Abstract: A fuel assembly upper cap (6) comprising a transverse adapter plate (6a) with apertures (8) for attaching guide tubes (4) and apertures (9) enabling water to flow therethrough. The water flow apertures (9a) located in the central portion of the adapter plate (6a) of the upper cap (6) are triangular with rounded corners and uniformly distributed around some or all of the apertures (8) for attaching the guide tubes (4).

    Abstract translation: 一种燃料组件上盖(6),包括具有孔(8)的横向适配器板(6a),用于附接引导管(4)和使水能够流过的孔(9)。 位于上盖(6)的适配板(6a)的中心部分的水流孔(9a)是三角形的,具有圆角,并且均匀地分布在一些或全部孔(8)周围,用于附接导管 4)。

    METHOD AND DEVICE FOR OPERATING A REACTOR IN AN UNSTABLE STATE
    274.
    发明申请
    METHOD AND DEVICE FOR OPERATING A REACTOR IN AN UNSTABLE STATE 审中-公开
    方法和设备操作的反应器在不稳定的情况

    公开(公告)号:WO1996021929A1

    公开(公告)日:1996-07-18

    申请号:PCT/DE1996000014

    申请日:1996-01-08

    Abstract: In order to stabilize a transient instability in a boiling-water reactor, the invention calls for the oscillating neutron flux to be measured and, when it exceeds a first limit over several periods of oscillation, for the rate of increase of the oscillation to be determined. When a further limit (in particular one depending on the rate of increase) of the oscillating flux is exceeded, one of a number of stabilization strategies is selected, as a function of the rate of increase, in order to produce premature stabilization of the oscillation. A hierarchy of stabilization options is available: blocking a power increase in the control system, slow controlled lowering of the power, or rapid power reduction by a partial SCRAM. The unstable condition is monitored by a system of sensors distributed over the reactor core, each of which redundantly measures the flux in a part of the core. The sensors act on several redundantly operating systems, the signal from each sensor being effective in only one of these systems.

    Abstract translation: 为了衰减沸水反应堆的瞬时不稳定状态,振荡中子通量进行测量,并将振荡的增加超过在多个振荡周期的第一阈值后的速率。 根据增加的范围内的不同的稳定化策略的速率超过另一个(尤其是依赖于增加的速率)限制的振荡流后采取,阻尼振荡在早期阶段,需要紧急停堆之前。 有稳定措施层次结构是可用的:阻挡由“部分SCRAM”中的控制控制的减速行驶性能,快速减少电力的电力的增加。 不稳定状态的监测是通过分布在冗余分别测量在所述芯部的区域中的流动的核心传感器的系统来完成。 传感器从而作用于多个冗余工作的系统中,每个传感器的信号是有效的只有这些冗余系统的一个单一的。

    METHOD FOR DESIGNING GAS TAG COMPOSITIONS
    276.
    发明申请
    METHOD FOR DESIGNING GAS TAG COMPOSITIONS 审中-公开
    气体标签组合物的设计方法

    公开(公告)号:WO1995018450A1

    公开(公告)日:1995-07-06

    申请号:PCT/US1994014910

    申请日:1994-12-23

    CPC classification number: G21C17/042 G21Y2002/201 G21Y2002/204 G21Y2004/40

    Abstract: For use in the manufacture of gas tags such as employed in a nuclear reactor gas tagging failure detection system, a method for designing gas tagging compositions utilizes an analytical approach wherein the final composition of a first canister of tag gas as measured by a mass spectrometer is designated as node #1. Lattice locations of tag nodes in multi-dimensional space are then used in calculating the compositions of a node #2 and each subsequent node so as to maximize the distance of each node from any combination of tag components which might be indistinguishable from another tag composition in a reactor fuel assembly. Alternatively, the measured compositions of tag gas numbers 1 and 2 may be used to fix the locations of nodes 1 and 2, with the locations of nodes 3-N then calculated for optimum tag gas composition. A single sphere defining the lattice locations of the tag nodes may be used to define approximately 20 tag nodes, while concentric spheres can extend the number of tag nodes to several hundred.

    Abstract translation: 为了用于制造用于核反应堆气体标签故障检测系统的气体标签,用于设计气体标签组合物的方法采用分析方法,其中通过质谱仪测量的标签气体的第一罐的最终组成为 指定为节点#1。 然后将多维空间中的标签节点的格子位置用于计算节点#2和每个后续节点的组合,以便最大化每个节点与标签组件的任何组合的距离,标签组件可能与另一个标签组合无法区分 反应堆燃料组件。 或者,标记气体号1和2的测量组合物可用于固定节点1和2的位置,然后针对最佳标签气体组成计算节点3-N的位置。 可以使用限定标签节点的格子位置的单个球来定义大约20个标签节点,而同心球体可以将标签节点的数量扩展到数百个。

    A BWR FUEL ASSEMBLY
    277.
    发明申请
    A BWR FUEL ASSEMBLY 审中-公开
    BWR燃油总成

    公开(公告)号:WO1995015564A1

    公开(公告)日:1995-06-08

    申请号:PCT/US1993011663

    申请日:1993-12-02

    Abstract: A boiling water nuclear reactor used for the production of electicity includes fuel rods (328A) and an assembly of these fuel rods that improve the reactor economics and safety. The fuel assemblies include hydride fuel pellets (636) at selected axial and radial positions in addition to oxide fuel pellets. The hydride fuel functions simultaneously as a fuel and as a moderator. The hydride fuel can be made from different combinations of fissionable materials such as uranium, and hydrides such as zirconium hydride. The fuel (such as U-ZrH1.6) is substituted for oxide fuel (UO2) in undermoderated regions of the core. Hydride fuel rods also replace water rods in the fuel assemblies. The use of hydrogen containing fuel rods and fuel assemblies enable flattening the power distribution across the fuel assembly and across the core; reducing the need for power shaping and reactivity control with burnable poisons and control rods; improving the nuclear fuel utilization; increasing the reactor availability; increasing the safety factors for fuel meltdown accidents or, alternatively, increasing the power output from a given size core; reducing the cold shutdown reactivity margin; and reducing the leakage of neutrons from the core.

    Abstract translation: 用于生产电气的沸水核反应堆包括燃料棒(328A)和这些燃料棒的组件,其提高了反应堆的经济性和安全性。 除了氧化物燃料颗粒之外,燃料组件还包括在选定的轴向和径向位置的氢化物燃料颗粒(636)。 氢化物燃料同时作为燃料和作为调节剂。 氢化物燃料可以由可裂变材料如铀和氢化物如氢化锆的不同组合制成。 燃料(如U-ZrH1.6)代替核心的未掺杂区域的氧化物燃料(UO2)。 氢化物燃料棒还代替燃料组件中的水棒。 使用含氢燃料棒和燃料组件可以使整个燃料组件和核心的功率分布平坦化; 减少对可燃毒物和控制棒的功率整形和反应性控制的需求; 提高核燃料利用率; 增加反应堆的可用性; 增加燃料熔断事故的安全因素,或者增加给定尺寸核心的功率输出; 降低冷关闭反应裕度; 并减少中子从核心泄漏。

    NUCLEAR FUEL CYCLE
    278.
    发明申请
    NUCLEAR FUEL CYCLE 审中-公开
    核燃料循环

    公开(公告)号:WO1995011509A1

    公开(公告)日:1995-04-27

    申请号:PCT/JP1994001745

    申请日:1994-10-18

    Abstract: A method of cycling a nuclear fuel for a fast breeder and a minor actinoids annihilation reactor, which provides a nuclear fuel cycle having technical advantages, such as a safety inherent in a nuclear reactor, a short fuel doubling time and a high uranium resources utilization factor, and economical advantages, comprising the steps of: preparing sphere pack type fuel pins including a nuclear fuel containing uranium-plutonium-mixed nitride fuel and a minor actinoids nitride fuel, and a sodium heat bonding material, installing the fuel pins in a reactor core and burning the same, subjecting the used fuel to fused salt electrolysis, converting the uranium, plutonium and minor actinoids deposited on a cathode into a high-order nitride, recovering the high-order nitride, converting the recovered high-order nitride into mononitride, and manufacturing a nuclear fuel, which contains a uranium-plutonium-mixed nitride fuel and a minor actinoids nitride fuel, from the mononitride.

    Abstract translation: 一种为快速繁殖者和一个小型锕系湮灭反应堆循环核燃料的方法,其提供具有技术优势的核燃料循环,例如核反应堆固有的安全性,短燃料倍增时间和高铀资源利用因子 以及经济的优点,包括以下步骤:制备包括含有铀 - 钚混合氮化物燃料和次要激发态氮化物燃料的核燃料的球形包装型燃料销和钠热粘合材料,将燃料销安装在反应堆堆芯 并对其进行燃烧,使用过的燃料进行熔融盐电解,将沉积在阴极上的铀,钚和次要锕系化为高级氮化物,回收高级氮化物,将回收的高氮氮化物转化成单硝化物, 并且从单硝化物制造含有铀 - 钚混合氮化物燃料和次要的激发态氮化物燃料的核燃料。

    PASSIVE DECAY HEAT REMOVAL AND INTERNAL DEPRESSURIZATION SYSTEM FOR NUCLEAR REACTORS
    279.
    发明申请
    PASSIVE DECAY HEAT REMOVAL AND INTERNAL DEPRESSURIZATION SYSTEM FOR NUCLEAR REACTORS 审中-公开
    被动反应器的被动去除和内部去除系统

    公开(公告)号:WO1995010836A1

    公开(公告)日:1995-04-20

    申请号:PCT/US1994011643

    申请日:1994-10-07

    Abstract: A jet condenser (30) injects steam from a steam generator (10) into a mixing tube (50), where it combines with coolant water from a heat exchanger (32). The steam completely condenses upon mixing with the water because the ratio of the mass flow rate of water to that of steam is relatively high at any given combination of temperatures and pressures. The mixture of coolant water and condensate then enters a divergent tube (52). This action enhances dynamic natural convection in the condenser loop (39), which provides the forces that move the water through the loop (39). A small portion of the water is returned to the steam generator (10); the remainder is diverted to the heat exchanger (32). The mass flow of the steam in the jet condenser (30) is equal to that of the condensate returned to the steam generator (10), thereby maintaining a constant coolant water inventory. During an accident, radioactive fission products would be retained within the closed jet condenser loop (39).

    Abstract translation: 喷射冷凝器(30)将来自蒸汽发生器(10)的蒸汽喷射到混合管(50)中,其中与来自热交换器(32)的冷却水结合。 在与水混合时,蒸汽完全冷凝,因为在任何给定温度和压力的组合下,水的质量流量与蒸汽的质量流量之比相对较高。 冷却水和冷凝水的混合物然后进入发散管(52)。 这种作用增强了冷凝器回路(39)中的动态自然对流,其提供使水通过回路(39)的力。 一小部分水返回到蒸汽发生器(10); 剩余部分被转移到热交换器(32)。 喷射冷凝器(30)中的蒸汽的质量流量等于返回到蒸汽发生器(10)的冷凝物的质量流量,从而保持恒定的冷却剂水库存。 在事故期间,放射性裂变产物将被保留在封闭的射流冷凝器回路(39)内。

    CONTROL ROD FOR NUCLEAR REACTOR
    280.
    发明申请
    CONTROL ROD FOR NUCLEAR REACTOR 审中-公开
    核反应堆控制棒

    公开(公告)号:WO1995008828A1

    公开(公告)日:1995-03-30

    申请号:PCT/SE1994000869

    申请日:1994-09-19

    Inventor: ABB ATOM AB

    Abstract: The invention relates to a control rod for a boiling water reactor. The control rod comprises a top piece and a bottom piece between which an absorber part is arranged. The absorber part comprises a central part (4) and four absorber blades (3) extending from the central part (4). The absorber part comprises a channel (10) which comprises the central part and which extends along the length of the whole absorber part. The channel is surrounded by walls of a neutron-absorbing material with a long service life, for example hafnium. The channel is at least partially filled with a moderator, for example light water. During the manufacture the absorber part has undergone a heat treatment such that the hafnium alloy has been completely or partially transformed from alpha -phase to beta -phase and thereafter been rapidly cooled to alpha -phase.

    Abstract translation: 本发明涉及一种用于沸水反应器的控制棒。 控制杆包括顶部件和底部件,其间布置吸收器部件。 吸收器部分包括从中心部分(4)延伸的中心部分(4)和四个吸收叶片(3)。 吸收器部分包括通道(10),该通道(10)包括中心部分并且沿着整个吸收体部分的长度延伸。 通道被具有长寿命的中子吸收材料的壁所包围,例如铪。 通道至少部分地装有调节剂,例如淡水。 在制造过程中,吸收体部分已进行热处理,使得铪合金已经完全或部分地从α相转变成β相,然后迅速冷却成α相。

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