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公开(公告)号：US4767595A
公开(公告)日：1988-08-30
申请号：US49897
申请日：1987-05-15
CPC分类号： G21C7/00 , G21C3/324 , G21C5/02 , G21C3/334 , G21Y2002/201 , G21Y2004/30 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： In a boiling water reactor (BWR) of the D-lattice type an improved apparatus and method for the mounting of a nuclear fuel assembly is disclosed. Specifically, a D-lattice nuclear fuel assembly is diagonally displaced at the top and diagonally displaced at the bottom to and toward the cruciform shaped control rod interstices. Displacement at the bottom end of the nuclear fuel assembly occurs by an eccentrically centered lower tie plate and fluid inlet for fitting to the core plate at the bottom end of the assembly. Displacement at the top end of the nuclear fuel assembly occurs by shims in the vicinity of the upper end of the channel at the top guides. The disclosed channel assembly is capable of installation during refueling cycles, with a displaced channel being substituted for prior art conventional D-lattice channels. Substitution of one displaced channel occurs with each refueling cycle in a group of four channels. Consequently, there results at the end a maximum of four refueling cycles, complete installation of the displaced channels. As substitution occurs, there results an improved worth of each fuel channel assembly enabling an eventual aggregate 2% increase in life with resultant savings.
摘要翻译： 公开了一种用于安装核燃料组件的改进的装置和方法，在D-晶格型沸水反应器（BWR）中。 具体地说，D格子核燃料组件在顶部是斜对位移的，并且在底部向对角线位移并且朝向十字形控制棒间隙。 在核燃料组件的底端的位移由偏心中心的下连接板和流体入口发生，用于在组件的底端装配到芯板。 在核燃料组件的顶端的位移通过在顶部引导件处的通道的上端附近的垫片发生。 所公开的通道组件能够在加油循环期间安装，其中替换通道代替现有技术的常规D-晶格通道。 在一组四个通道中的每个加油循环中，替换一个位移通道。 因此，最终导致最多四个加油循环，完全安装排水通道。 随着替代发生，每个燃料通道组件的价值得到改善，从而最终总体上增加了2％的增长，从而节约了成本。
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公开(公告)号：US5017332A
公开(公告)日：1991-05-21
申请号：US375646
申请日：1989-07-03
CPC分类号： G21C3/322 , G21C3/328 , G21Y2002/201 , G21Y2002/207 , G21Y2004/30 , G21Y2004/302 , Y02E30/31 , Y02E30/38
摘要： In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are shortened with respect to the remaining rods and are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. The partial length rods extend from the bottom of the fuel bundle and terminate within the boiling region. during shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle. Shutdown control rod worth is improved due to greater moderator-to-fuel ratio and a longer thermal neutron diffusion length. During power reator operation, the partial length fuel rods improve flow distribution above the ends of the partial length rods by channeling steam in the open interstitial area between rods above the ends of the partial length rods. This enables a high slip ratio of steam with respect to water and increases the density of the moderating water about the remaining rods in the upper region of the bundle at power operation. The total pressure drop is reduced, permitting more fuel rods in the design or a larger fuel rod diameter. The ratio of two-phase pressure drop to single phase pressure drop also is reduced, tending to increase the threshold for thermal hydraulic instability or coupled nucler-thermal-hydraulic instability. Rod spacers and bundle tie plates are provided with larger apertures overlying the partial length rods for further channeling of the steam and reduction of two-phase pressure drop. Most importantly and during full reactor power output, the pressure drop in the two-phase region of the bundle is reduced without substantial corresponding degradation of the fuel assemblies thermal limits. These features permit designs with larger fuel rod diameter than are possible without part length rods and results in a net increase in fuel assembly uranium weight with the larger fuel rod diameter more than compensating for the weight removed by shortening some of the fuel rods.
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3.发明授权Fuel assembly structure selectively using channel and coolant rod for load support and method 失效燃料组件结构选择性地使用通道和冷却剂棒进行负载支持和方法
公开(公告)号：US5748695A
公开(公告)日：1998-05-05
申请号：US551769
申请日：1995-11-07
CPC分类号： G21C3/3315 , G21C3/331 , G21Y2002/304 , G21Y2002/402 , G21Y2004/30 , Y02E30/40
摘要： A latch pin assembly is configured to enable selective engagement with at least one of the fuel assembly channel and the coolant rod such that the fuel assembly channel and the coolant rod can be selectively utilized to support the fuel assembly load, thereby eliminating the need for fuel tie rods. The latch pin assembly includes a latch pin selectively engageable with the fuel assembly channel and the coolant rod, and an anchoring assembly cooperating with the latch pin, wherein the anchoring assembly anchors the latch pin in a selected position such that the latch pin engages at least one of the fuel assembly channel and the coolant rod. The latch pin may be alternatively engageable with the fuel assembly channel and the coolant rod or simultaneously engageable with the fuel assembly channel and the coolant rod. With this arrangement, the bail handle can be used both to remove the entire assembly including the fuel assembly channel from the reactor vessel or to remove only the fuel bundle from the reactor vessel, leaving the fuel assembly channel in place.
摘要翻译： 闩锁销组件被构造成使得能够与燃料组件通道和冷却剂棒中的至少一个选择性地接合，使得可以选择性地利用燃料组件通道和冷却剂棒来支撑燃料组件负载，从而消除对燃料的需要 拉杆。 闩锁销组件包括可选择地与燃料组件通道和冷却剂杆接合的闩锁销以及与闩锁销配合的锚固组件，其中锚定组件将闩锁销锚定在选定位置，使得闩锁销至少接合 燃料组件通道和冷却剂棒之一。 闩锁销可以可选地与燃料组件通道和冷却剂杆接合，或者可以与燃料组件通道和冷却剂棒同时接合。 通过这种布置，吊环把手可用于从反应堆容器中移除包括燃料组件通道的整个组件，或仅从反应堆容器移除燃料束，使燃料组件通道保持在适当位置。
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公开(公告)号：US5112570A
公开(公告)日：1992-05-12
申请号：US176975
申请日：1988-04-04
CPC分类号： G21C3/322 , G21C3/328 , G21Y2002/201 , G21Y2004/30 , G21Y2004/302 , Y02E30/31 , Y02E30/38
摘要： In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. During shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle. Shutdown control rod worth is improved due to greater moderator-to-fuel ratio and a longer thermal neutron diffusion length. During power reactor operation, the partial length fuel rods improve flow distributions above the ends of the partial length rods by channeling steam in the open interstitial area between rods above the ends of the partial length rods.
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公开(公告)号：US5787140A
公开(公告)日：1998-07-28
申请号：US654957
申请日：1996-05-29
CPC分类号： G21C3/334 , G21C3/324 , G21Y2002/201 , G21Y2002/301 , G21Y2002/303 , G21Y2004/302 , G21Y2004/305 , Y02E30/40
摘要： A fuel bundle assembly for a nuclear reactor includes a modified channel that improves pressure drop performance and a handle assembly that includes structure for preventing a broken end plug from escaping the fuel bundle. In modifying the channel, one approach is to vary the outside dimension of the fuel channel along the length of the channel, but maintain a constant channel wall thickness. Another approach is to maintain the external dimensions of the fuel channel and vary the wall thickness along the length of the channel. The handle assembly replaces the conventional upper tie plate and is provided with structure for preventing debris such as a broken fuel rod end plug from escaping the fuel bundle. The structure preferably includes a plurality of gridwork cross members forming a substantially square grid including gridwork windows that are sized smaller than the fuel rod end plugs.
摘要翻译： 用于核反应堆的燃料束组件包括改进压降性能的改进通道和包括防止破坏的端塞从燃料束逸出的结构的手柄组件。 在修改通道时，一种方法是沿着通道的长度改变燃料通道的外部尺寸，但是保持恒定的通道壁厚度。 另一种方法是保持燃料通道的外部尺寸并沿着通道的长度改变壁厚度。 手柄组件取代了常规的上连接板，并且设置有用于防止诸如破坏的燃料棒端塞的碎屑从燃料束逸出的结构。 该结构优选地包括多个格栅横向构件，其形成大致正方形的格栅，包括尺寸小于燃料棒端塞的格栅窗。
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6.发明授权Handle unit for a fuel assembly in a nuclear reactor and fuel assembly having modified channel 失效用于核反应堆中燃料组件的处理单元和具有改进通道的燃料组件
公开(公告)号：US5809101A
公开(公告)日：1998-09-15
申请号：US655875
申请日：1996-05-29
摘要： A fuel bundle assembly for a nuclear reactor includes a modified channel and a handle unit that improves pressure drop performance. With the modified channel, one approach is to vary the outside dimension of the fuel channel along the length of the channel, but maintain a constant channel wall thickness. Another approach is to maintain the external dimensions of the fuel channel and vary the wall thickness along the length of the channel. The handle unit is formed including a handle member and a separate rod support member releasably engageable with the handle member. The handle member includes channels for receiving latch pin assemblies, coolant rods and a spacer assembly. The rod support member includes a plurality of fuel rod support chambers providing lateral support for the fuel rods of the fuel assembly. The rod support member also includes a main chamber that is sized to receive a portion of the handle member in a friction fit. In addition to providing improved pressure drop performance, the arrangement eliminates the need to realign the fuel rods in an upper tie plate or an upper spacer when access to the fuel rods is necessary. In addition, the handle unit serves to prevent failed end plugs from escaping the fuel bundle.
摘要翻译： 用于核反应堆的燃料束组件包括改进的通道和提高压降性能的手柄单元。 使用改进的通道，一种方法是沿通道的长度改变燃料通道的外部尺寸，但是保持恒定的通道壁厚度。 另一种方法是保持燃料通道的外部尺寸并沿着通道的长度改变壁厚度。 手柄单元形成为包括手柄构件和可释放地与手柄构件接合的单独的杆支撑构件。 手柄构件包括用于接收闩锁销组件，冷却剂棒和间隔件组件的通道。 杆支撑构件包括多个燃料棒支撑室，为燃料组件的燃料棒提供侧向支撑。 杆支撑构件还包括主室，其尺寸适于以摩擦配合接收手柄构件的一部分。 除了提供改进的降压性能之外，当需要进入燃料棒时，该布置消除了在上连接板或上隔板中重新对准燃料棒的需要。 此外，手柄单元用于防止失效的端塞从燃料束逸出。
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