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Fast burst nuclear reactor

机译:快爆核反应堆

摘要

1,147,290. Reactors. UNITED STATES ATOMIC ENERGY COMMISSION. 8 March, 1968 [8 May, 1967], No. 11333/68. Heading G6C. A pulsed nuclear reactor for producing bursts of fast neutrons comprises a molten salt fuel floating on a liquid metal coolant which is used to raise the fuel into an active core region surrounded by a neutron reflector. The molten salt becomes supercritical within the active core region, emits a short intense burst of fast neutrons, and then returns to a subcritical condition. As shown in Fig. 1, the reactor containment vessel comprises an upper section 1 and a lower section 2 communicating through a centrally positioned tubulation 3. The active core region 4 is surrounded by a graphite reflector 5 and a container-reflector 6 which is the upper end portion of the tubulation 3. The molten salt fuel 7 preferably comprises a LiF-UF 4 mixture, and molten Pb is preferred as the liquid metal coolant 8. Test materials to be exposed to neutron irradiation are disposed within a test cavity 16 located centrally within the core region 4. The fuel 7 which floats on the coolant 8 is driven upward through the tubulation 3 by means of a pulse of pressurized gas injected through a conduit 20 into the annular region 19 between the tubulation 3 and the lower section 2 of the containment vessel. When the fuel level is approximately three inches below the top of the reflector 5, the reactor becomes critical on prompt neutrons. As the remainder of the core region 4 fills, the reactor becomes supercritical to provide the desired burst of fast neutrons, the fuel temperature increasing rapidly causing the reactor to become subcritical due to the negative temperature coefficient of reactivity of the fuel. As the molten lead 8 continues to rise, the molten salt fuel 7 overflows into a heat exchange region 9 where it is cooled by direct contact with relatively cool molten lead pumped through piping 22 to discharge manifolds 10, 11. The heated lead flows through an air-cooled heat exchanger 23 and a freeze valve 24. When the entire mass of molten salt fuel 7 has been cooled to the starting temperature of 500‹ C., the freeze valve 24 is closed while pump 21 continues pumping lead into the region 9, thus displacing the fuel upward so as to flow back over the reflector 5 and down through the core region 4 to accumulate in the tubulation 3 where it floats on the coolant 8. The reactor is then ready for generating a new burst of neutrons. Deflecting vanes 12 disposed immediately above and annular plates 13 disposed immediately below the core region 4 contain material having a high neutron absorption cross-section, the former rapidly terminating the neutron chain reaction occurring in the molten salt fuel as it leaves the core region and the latter preventing the premature development of a chain reaction in the fuel before it enters the core region. Tiers of inverted cups (15) (Fig. 3, not shown) are supported by braces 14 within the core region 4, the cups retaining a portion of the expanding molten salt fuel and preventing its leaving the core region so as to partially compensate for the very large negative temperature of reactivity of the fuel. The cups are not completely filled and the size of the resulting voids is reduced during the neutron burst by the expanding fuel causing a positive reactivity insertion to occur due to the negative void coefficient of reactivity of the reactor. By proper selection of the number and size of the inverted cups and the pressure within the reactor prior to a burst, the negative temperature coefficient which is operative on the burst may be regulated to achieve the desired burst size.
机译:1,147,290。反应堆。美国原子能委员会。 1968年3月8日[1967年5月8日],第11333/68号。标题G6C。用于产生快速中子爆发的脉冲核反应堆包括漂浮在液态金属冷却剂上的熔融盐燃料,该熔盐燃料用于将燃料提升到被中子反射器包围的有源堆芯区域。熔融盐在活性芯区域内变为超临界状态,发出快速中子的短时强烈爆发,然后返回至亚临界状态。如图1所示,反应堆安全壳包括通过中央定位管3连通的上部1和下部2。活性芯区域4被石墨反射器5和容器反射器6包围,容器反射器6是石墨容器。管3的上端部分。熔融盐燃料7优选地包括LiF-UF 4混合物,并且熔融Pb优选地作为液态金属冷却剂8。要暴露于中子辐射的测试材料被放置在位于以下位置的测试腔16内。漂浮在冷却剂8上的燃料7借助于通过管道20注入到管3和下部2之间的环形区域19中的加压气体的脉冲被向上驱动通过管3。安全壳。当燃料水平低于反射器5顶部约3英寸时,反应堆对迅速中子变得至关重要。随着堆芯区域4的其余部分填充,反应堆变得超临界以提供所需的快速中子爆发,燃料温度迅速升高,由于燃料的反应性为负温度系数,导致反应堆变为亚临界。随着熔融铅8继续上升,熔融盐燃料7溢出到热交换区域9中,在那里通过与通过管道22泵送至歧管10、11的相对较冷的熔融铅直接接触而被冷却。空气冷却的热交换器23和一个冷冻阀24。当熔融盐燃料7的整体质量已冷却到起始温度500°C时,关闭冷冻阀24,同时泵21继续将铅泵入区域9从而使燃料向上移位,从而流回反射器5上并向下流经核心区域4,从而在管道3中积聚,燃料在管道3中漂浮在冷却剂8上。然后,反应堆就准备好产生新的中子爆发。紧靠核心区域4上方设置的导流叶片12和紧靠核心区域4下方设置的环形板13包含具有高中子吸收横截面的材料,前者在熔融盐燃料离开核心区域时迅速终止中子链反应。后者防止燃料在进入核心区之前过早地发生链式反应。倒杯(15)的层(图3,未示出)由核心区域4内的支架14支撑,杯将一部分膨胀的熔融盐燃料保持并防止其离开核心区域,从而部分补偿燃料反应性非常大的负温度。杯未完全充满,并且在中子爆裂期间,膨胀的燃料减小了所产生的空隙的尺寸,由于反应堆的空隙反应系数为负,导致正反应性插入发生。通过倒置杯的数量和尺寸以及之前的突发反应器内的压力的适当选择,负温度系数这是对脉冲串操作可以被调节,以实现期望的突发大小。

著录项

  • 公开/公告号GB1147290A

    专利类型

  • 公开/公告日1969-04-02

    原文格式PDF

  • 申请/专利权人 UNITED STATES ATOMIC ENERGY COMMISSION;

    申请/专利号GB19680011333

  • 发明设计人

    申请日1968-03-08

  • 分类号G21C1;G21C1/02;G21C1/22;G21C1/30;G21C7/02;G21C7/30;

  • 国家 GB

  • 入库时间 2022-08-23 11:52:33

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