公开(公告)号：US07760842B2

公开(公告)日：2010-07-20

申请号：US11512938

申请日：2006-08-29

Applicant: Sture Helmersson ,  Mahdi Majed ,  Gunilla Norbäck ,  Dmitry Paramonov ,  Rolf Eklund ,  Carl Adamsson

Inventor： Sture Helmersson ,  Mahdi Majed ,  Gunilla Norbäck ,  Dmitry Paramonov ,  Rolf Eklund ,  Carl Adamsson

IPC: G21C9/00

CPC classification number: G21D3/001 ,  G21C17/02 ,  G21D3/04 ,  G21D3/08 ,  G21Y2002/204 ,  G21Y2002/304 ,  G21Y2004/40 ,  Y02E30/40

Abstract: The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product (23) and a method of operating a nuclear energy plant.

Abstract translation: 本发明涉及一种在沸水反应堆类型的核水反应堆中估计何时可能出现干燥的方法。 该方法包括使用表达核反应堆的局部干燥性质的配方。 该公式包括至少第一和第二因素。 第一个因素是描述干燥特性如何依赖于通过核燃料装置的冷却介质的流动的第一个功能。 第二个因素是第二个功能，描述了干燥特性如何依赖于核燃料装置的轴向功率分布。 第一和第二功能描述了彼此独立的所述流动依赖性和所述轴向功率分布依赖性。 本发明还涉及核能装置，计算机程序产品（23）和操作核能装置的方法。

公开(公告)号：US20100158185A1

公开(公告)日：2010-06-24

申请号：US11512938

申请日：2006-08-29

Applicant: Sture Helmersson ,  Mahdi Majed ,  Gunilla Norback ,  Dmitry Paramonov ,  Rolf Eklund ,  Carl Adamsson

Inventor： Sture Helmersson ,  Mahdi Majed ,  Gunilla Norback ,  Dmitry Paramonov ,  Rolf Eklund ,  Carl Adamsson

IPC: G21C17/00

CPC classification number: G21D3/001 ,  G21C17/02 ,  G21D3/04 ,  G21D3/08 ,  G21Y2002/204 ,  G21Y2002/304 ,  G21Y2004/40 ,  Y02E30/40

Abstract: The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product (23) and a method of operating a nuclear energy plant.

Abstract translation: 本发明涉及一种在沸水反应堆类型的核水反应堆中估计何时可能出现干燥的方法。 该方法包括使用表达核反应堆的局部干燥性质的配方。 该公式包括至少第一和第二因素。 第一个因素是描述干燥性能如何依赖于通过核燃料装置的冷却介质的流动的第一个功能。 第二个因素是第二个功能，描述了干燥特性如何依赖于核燃料装置的轴向功率分布。 第一和第二功能描述了彼此独立的所述流动依赖性和所述轴向功率分布依赖性。 本发明还涉及核能装置，计算机程序产品（23）和操作核能装置的方法。

公开(公告)号：US20100142667A1

公开(公告)日：2010-06-10

申请号：US12440633

申请日：2007-08-21

Applicant: Sture Helmersson

Inventor： Sture Helmersson

IPC: G21C19/10 ,  G21C19/42 ,  G21C3/322

CPC classification number: G21C19/04 ,  G21C19/10 ,  G21Y2002/207 ,  G21Y2002/303 ,  G21Y2004/30 ,  G21Y2004/40

Abstract: The invention refers to a device and a method for handling a fuel assembly (3), which comprises a number of fuel rods extending between a lower part and an upper part of the fuel assembly, a debris filter located in the lower part of the fuel assembly and a casing surrounding the fuel rods. The device comprises a lifting device (15) for engaging, during a lifting operation, a fuel assembly located in a reactor vessel (1) and lifting the fuel assembly upwards and out from the reactor vessel. A conduit member is connected to the upper part of the fuel assembly. A pump (32) creates a flow of water through the conduit member and the fuel assembly during the lifting operation. The flow has such a size that possible debris particles contained in and/or immediately beneath the debris filter at least are retained in and/or immediately beneath the debris filter during the iifting operation.

Abstract translation: 本发明涉及一种用于处理燃料组件（3）的装置和方法，燃料组件（3）包括在燃料组件的下部和上部之间延伸的多个燃料棒，位于燃料的下部的碎屑过滤器 组件和围绕燃料棒的套管。 该装置包括提升装置（15），用于在提升操作期间接合位于反应器容器（1）中的燃料组件，并将燃料组件从反应器容器向上和向外提升。 导管构件连接到燃料组件的上部。 泵（32）在提升操作期间通过导管构件和燃料组件产生水流。 该流动具有这样的尺寸，使得容纳在碎屑过滤器中和/或紧邻碎片过滤器之下的可能的碎屑颗粒在移动操作期间至少保留在碎屑过滤器的和/或紧邻下方。

公开(公告)号：US20070002998A1

公开(公告)日：2007-01-04

申请号：US10569860

申请日：2004-08-30

Applicant: Sture Helmersson ,  Par Beccau

Inventor： Sture Helmersson ,  Par Beccau

IPC: G21C19/00

CPC classification number: G21D3/00 ,  G21C7/08 ,  G21Y2002/50 ,  G21Y2004/40 ,  Y02E30/39

Abstract: The invention refers to a method for operating a nuclear light water reactor during an operation cycle including a cardinal cycle and a number of successive control rod cycles. The reactor includes a plurality of elongated fuel units containing a nuclear fuel in the form a fissible material, a burnable absorber, and a plurality of control rods introduceable in a respective control rod position. Substantially all control rods are introduced in the core before the reactor is started and an operation cycle is initiated. The reactor is operated during the cardinal cycle with a first control rod configuration with a first group of control rods at least partly introduced and the remaining control rods extracted. The reactor is operated during the subsequent control rod cycles with a respective control rod configuration which each includes a different group of control rods at least partly introduced, wherein the cardinal cycle is substantially longer than each of the subsequent control rod cycles.

Abstract translation: 本发明涉及在操作循环中操作核水反应堆的方法，包括基本循环和多个连续的控制棒循环。 反应器包括多个细长的燃料单元，其包含可燃材料形式的核燃料，可燃性吸收器和可在相应控制杆位置引入的多个控制棒。 在反应器启动之前，基本上所有的控制棒都被引入到核心中，并且开始了一个操作循环。 反应器在基本循环期间以第一控制杆配置运行，第一组控制杆至少部分地被引入并且剩余的控制杆被提取。 反应器在随后的控制杆循环期间操作，具有相应的控制杆配置，每个控制杆配置包括至少部分地引入的不同组的控制杆，其中基本循环基本上比随后的每个控制杆循环更长。

公开(公告)号：US06353652B1

公开(公告)日：2002-03-05

申请号：US09180151

申请日：1999-02-24

Applicant: Sture Helmersson

Inventor： Sture Helmersson

IPC: G21C332

CPC classification number: G21C3/328 ,  G21Y2002/206 ,  Y02E30/31 ,  Y02E30/38

Abstract: A fuel assembly for a boiling water reactor comprising full-length fuel rods (3a, 3c) with a first length extending over the height of the entire fuel assembly, and part-length fuel rods (3b) with a second length extending only in the lower part (10) of the fuel assembly, the fuel rods which have positions immediately adjacent to the part-length fuel rods being adapted so as to be bent inwards, in their upper part, towards the open region (15) which is formed above the part-length fuel rods. At least half of the fuel rods in the fuel assembly are straight.

Abstract translation: 一种用于沸水反应堆的燃料组件，包括具有在整个燃料组件的高度上延伸的第一长度的全长燃料棒（3a，3c），以及具有第二长度的部分长度的燃料棒（3b） 燃料组件的下部（10），具有紧邻部分长度燃料棒的位置的燃料棒适于在其上部向内弯曲，朝向上方形成的开放区域（15） 部分长度的燃料棒。 燃料组件中的至少一半的燃料棒是直的。

公开(公告)号：US20100111242A1

公开(公告)日：2010-05-06

申请号：US12595572

申请日：2008-04-07

Applicant: Sture Helmersson ,  Magnus Limbäck ,  Jonathan Wright

Inventor： Sture Helmersson ,  Magnus Limbäck ,  Jonathan Wright

IPC: G21C7/32 ,  G21C7/08

CPC classification number: G21D3/06 ,  G21Y2002/50 ,  G21Y2004/40 ,  Y02E30/40

Abstract: A method of operating a nuclear reactor is disclosed. The reactor (1) encloses a core having a plurality of fuel rods (9). Each fuel rod (9) includes a cladding and fuel pellets of a nuclear fuel. The fuel pellets are arranged in an inner space of the cladding leaving a free volume comprising an upper plenum, a lower plenum and a pellet-cladding gap. The reactor is operated at a normal power and a normal inlet sub-cooling during a normal state. The reactor is monitored for detecting a defect on the cladding of any of the fuel rods. The operation of the reactor is changed to a particular state after detecting such a defect. The particular state permits an increase of the free volume in the defect fuel rod. The reactor is operated at the particular state during a limited time period, after which the reactor is operated at the normal state.

Abstract translation: 公开了一种操作核反应堆的方法。 反应器（1）包围具有多个燃料棒（9）的芯体。 每个燃料棒（9）包括核燃料的包层和燃料颗粒。 燃料颗粒被布置在包层的内部空间中，留下自由体积，其包括上部增压室，下部增压室和颗粒包层间隙。 在正常状态下，反应器以正常功率运行，正常进气冷却。 监测反应器以检测任何燃料棒的包层上的缺陷。 在检测到这样的缺陷之后，反应器的操作变为特定状态。 该特定状态允许增加缺陷燃料棒中的自由体积。 反应器在特定状态下在有限的时间段内运行，此后反应器在正常状态下运行。

公开(公告)号：US20080025454A1

公开(公告)日：2008-01-31

申请号：US11629497

申请日：2005-06-01

Applicant: Magnus Limback ,  Kristina Ryttersson ,  Sture Helmersson

Inventor： Magnus Limback ,  Kristina Ryttersson ,  Sture Helmersson

IPC: G21C7/08

CPC classification number: G21C7/08 ,  G21C17/04 ,  G21D3/06 ,  Y02E30/39

Abstract: A reactor of a nuclear plant encloses a core having a plurality of fuel elements and a number of control rods. Each fuel element includes a plurality of fuel rods each including a cladding and nuclear fuel enclosed in an inner space of the cladding. Each control rod is insertable to and extractable from a respective position between or in respective fuel elements to influence the effect of the reactor. A method for operating the reactor includes operating the reactor at a normal effect during a normal state, monitoring the reactor for detecting a defect on the cladding of any fuel rod, reducing the effect of the reactor after the detection of a defect, operating the reactor during a particular state during a time period during which the reactor at least during a part time is operated at the reduced effect in relation to the normal effect, and extracting the inserted control rods after the time period for continuing operation of the reactor at substantially the normal state.

Abstract translation: 核电站的反应堆包围具有多个燃料元件和多个控制棒的芯。 每个燃料元件包括多个燃料棒，每个燃料棒包括封装在包层的内部空间中的包层和核燃料。 每个控制杆可插入到相应燃料元件之间或相应燃料元件中的相应位置并且可从其中提取，以影响反应器的效果。 用于操作反应器的方法包括在正常状态下以正常效应操作反应器，监测反应器以检测任何燃料棒的包壳上的缺陷，在检测到缺陷后降低反应器的作用，操作反应器 在特定状态期间，至少在一段时间内反应堆以相对于正常效应降低的效果运行的时间段内，以及在反应器的持续运行的时间段之后提取所插入的控制棒， 正常状态

公开(公告)号：US06516042B2

公开(公告)日：2003-02-04

申请号：US09202639

申请日：1999-02-05

Applicant: Sture Helmersson

Inventor： Sture Helmersson

IPC: G21C3322

CPC classification number: G21C3/322 ,  G21Y2004/302 ,  Y02E30/31 ,  Y02E30/38

Abstract: The invention relates to a fuel assembly for a boiling water reactor which is adapted, during operation of the reactor, to allow water to flow upwards through the fuel assembly while absorbing heat from a plurality of fuel rods, whereby part of the water is transformed into steam. The fuel assembly comprises a steam channel through which the steam flows through the fuel assembly. The steam channel (16a, 16b, 16c, 16d) consists of an empty volume which at least extends through part of the fuel assembly. The fuel assembly is designed such that the water and the steam are brought to rotate around the steam channel whereby the water is thrown away from the steam channel whereas the steam which is separated from the water flows upwards through the steam channel.

Abstract translation: 本发明涉及一种用于沸水反应器的燃料组件，其在反应器运行期间适于允许水向上流过燃料组件，同时从多个燃料棒吸收热量，由此部分水被转化成 蒸汽。 燃料组件包括蒸汽通道，蒸汽通过该蒸汽通道流过燃料组件。 蒸汽通道（16a，16b，16c，16d）由至少延伸穿过燃料组件的一部分的空的体积组成。 燃料组件被设计成使得水和蒸汽围绕蒸汽通道旋转，由此水被从蒸汽通道抛出，而与水分离的蒸汽向上流过蒸汽通道。

公开(公告)号：US07804931B2

公开(公告)日：2010-09-28

申请号：US10585910

申请日：2005-01-10

Applicant: Sture Helmersson ,  Leif Larsson ,  Olov Nylund ,  H{dot over (a)}kan Söderberg

Inventor： Sture Helmersson ,  Leif Larsson ,  Olov Nylund ,  H{dot over (a)}kan Söderberg

IPC: G21C3/34

CPC classification number: G21C3/3424 ,  G21C3/34 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/40

Abstract: The invention refers to a spacer for holding a number if elongated fuel rods intended to be located in a nuclear plant and to a fuel unit having such spacers. The spacer encloses a number of cells, which each has a longitudinal axis and is arranged to receive a fuel rod in such a way that the fuel rod extends in parallel with the longitudinal axis. Each cell is formed by a sleeve-like member. Each sleeve-like member is manufactured in a sheet-shaped material that is bent to the sleeve-like shape.

Abstract translation: 本发明涉及用于保持数量的间隔物，如果用于位于核电站中的细长燃料棒和具有这种间隔物的燃料单元。 间隔件包围多个单元，每个单元具有纵向轴线并且被布置成以使得燃料棒与纵向轴线平行延伸的方式容纳燃料棒。 每个单元由套筒状构件形成。 每个套筒状构件制成弯曲成套筒状的片状材料。

公开(公告)号：US20100111800A1

公开(公告)日：2010-05-06

申请号：US12603748

申请日：2009-10-22

Applicant: Edward J. Lahoda ,  Lars Hallstadius ,  Sture Helmersson ,  Sumit Ray

Inventor： Edward J. Lahoda ,  Lars Hallstadius ,  Sture Helmersson ,  Sumit Ray

IPC: C01F17/00 ,  C25B1/26 ,  C25B1/02 ,  C25C1/02

CPC classification number: B01D59/18 ,  B01D59/20

Abstract: A method of making Gd or Er isotopes from gaseous compounds containing —BH4 and —CH3BH3 ions involves making the Gd or Er compounds (24) in a solid state reactor (10), passing the gaseous compounds (24) to a separation process (16) to provide products enriched in the desired isotopes of Gd or Er heads and Gd or Er tails depleted in these desired isotopes and then reacting the Gd or Er heads and Gd or Er tails with chlorine in a reactor (18) to provide products of 157GdCl3, 155GdCl3 or 167ErCl3 enriched in Gd and Er isotopes.

Abstract translation: 由含有-BH4和-CH3BH3离子的气态化合物制造Gd或Er同位素的方法包括使Gd或Er化合物（24）在固态反应器（10）中，将气态化合物（24）通入分离过程（16 ）以提供富含Gd或Er头的所需同位素的产物和在这些所需同位素中耗尽的Gd或Er尾部，然后在反应器（18）中使Gd或Er头和Gd或Er尾与氯反应，以提供157GdCl 3的产物 ，155GdCl3或167ErCl3富集Gd和Er同位素。