公开(公告)号：US11942229B2

公开(公告)日：2024-03-26

申请号：US16851142

申请日：2020-04-17

Applicant: BWXT Advanced Technologies LLC

Inventor： Craig D. Gramlich

IPC: G21C3/16 ,  G21C3/22 ,  G21C21/00 ,  G21C3/04

CPC classification number: G21C3/22 ,  G21C21/00 ,  G21C3/04 ,  G21C3/16

Abstract: Fission reactor has a cladding encasing a heat generating source including a fissionable nuclear fuel composition. The heat generating source is offset from the surface of the cladding and molten metal is located within the void space formed by the offset. As a liquid, the molten metal will flow and occupy any contiguous network of void space within the fuel cavity and provides thermal transfer contact between the heat generating source and the cladding. The cladding separates the heat generating source and the molten metal from the primary coolant volume.

公开(公告)号：US20240013940A1

公开(公告)日：2024-01-11

申请号：US18471871

申请日：2023-09-21

Applicant: TerraPower, LLC

Inventor： Pavel Hejzlar ,  Peter McNabb

IPC: G21C21/00 ,  G21C13/04 ,  G21C13/024 ,  G21C5/10

CPC classification number: G21C21/00 ,  G21C13/04 ,  G21C13/024 ,  G21C5/10 ,  G21C15/185

Abstract: A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.

公开(公告)号：US20240013939A1

公开(公告)日：2024-01-11

申请号：US18123205

申请日：2023-03-17

Applicant: Atomos Nuclear and Space Corporation

Inventor： Lucas Brady Beveridge

IPC: G21C21/00

CPC classification number: G21C21/00

Abstract: A modular space reactor includes a plurality of sections, each section containing a component of an assembled reactor. Each section contains contents configured to be unable to sustain a fission chain reaction as an individual section and is configured to be separately launched into space from each other section. The sections are configured for assembly in space to form the assembled reactor configured for sustaining an active fission chain reaction only when all of the sections are assembled together. In embodiments, contents of a section include at least one of fissile fuel, reactivity control devices, neutron reflectors, neutron moderators, radiation shielding mechanisms, cooling systems, power conversion systems. In embodiments, the sections are further configured for disassembly in space for being separable for at least one of refueling, decommissioning, and disposal of the system so disassembled. In embodiments, the modular space reactor is configured to sustain radioactive chain reactions when assembled.

公开(公告)号：US11810680B2

公开(公告)日：2023-11-07

申请号：US17067425

申请日：2020-10-09

Applicant: BOSTON ATOMICS, LLC

Inventor： Enrique Velez Lopez ,  William Robb Stewart

IPC: G21C1/32 ,  G21C15/253 ,  G21C1/08 ,  G21C11/02 ,  G21C13/028 ,  G21C13/00 ,  G21C21/00 ,  G21C13/10 ,  G21C11/08

CPC classification number: G21C15/253 ,  G21C1/08 ,  G21C11/028 ,  G21C11/08 ,  G21C13/00 ,  G21C13/028 ,  G21C13/10 ,  G21C21/00 ,  G21C1/326

Abstract: The present disclosure is directed to systems and methods useful for the construction and operation of a Modular Integrated Gas High-Temperature Reactor (MIGHTR). The MIGHTR includes a reactor core assembly disposed at least partially within a core baffle within a first high-pressure shell portion, a thermal transfer assembly disposed at least partially within a flow separation barrel within a second high-pressure shell portion. The longitudinal axes of the first high-pressure shell portion and the second high-pressure shell portion may be collinear. The reactor core assembly may be accessed horizontally for service, maintenance, and refueling. The core baffle may be flexibly displaceably coupled to the flow separation barrel. Coolant gas flows through the reactor core assembly and into the thermal transfer assembly where the temperature of the coolant gas is reduced. A plurality of coolant gas circulators circulate the cooled coolant gas from the thermal transfer assembly to the reactor core assembly.

公开(公告)号：US10037822B2

公开(公告)日：2018-07-31

申请号：US15022834

申请日：2014-03-19

Applicant: Joint Stock Company “AKME-Engineering”

Inventor： Petr Nikiforovich Martynov ,  Radomir Shamilievich Askhadullin ,  Konstantin Dmitrievich Ivanov ,  Aleksandr Urievich Legkikh ,  Aleksey Nikolaevich Storozhenko ,  Aleksandr Ivanovich Filin ,  Sergey Viktorovich Bulavkin ,  Said Mirfaisovich Sharikpulov ,  Stepan Artemovich Borovitsky

IPC: G21C1/03 ,  G21C13/08 ,  G21C21/00 ,  C23C22/72 ,  C23C22/73 ,  G21C15/247 ,  G21C17/022

CPC classification number: G21C1/03 ,  C23C22/72 ,  C23C22/73 ,  G21C13/08 ,  G21C15/247 ,  G21C17/0225 ,  G21C21/00 ,  Y02E30/40

Abstract: The invention relates to the field of nuclear technology, and specifically to a method for the in situ passivation of steel surfaces. The method consists in installing, in a position intended for a regular core, a core simulator in the form of a model of the core, which models the shape thereof, the relative position of the core components, and also the mass characteristics thereof; next, the reactor is filled with a heavy liquid metal heat transfer medium, the heat transfer medium is heated to a temperature which provides for the conditions of passivation, and in situ passivation is carried out in two stages, the first of which includes an isothermal passivation mode in conformity with the conditions determined for this stage, and the second mode includes non-isothermal passivation, which is carried out under different conditions, after which the core simulator is removed and the regular core is installed in the place thereof. The method provides for the corrosion-resistance of steel elements in a heavy liquid metal heat transfer medium environment and permits a decrease in the maximum rate of oxygen consumption during the initial period of operation of a nuclear actor.

公开(公告)号：US20180105915A1

公开(公告)日：2018-04-19

申请号：US15538798

申请日：2016-01-29

Applicant: KEPCO NUCLEAR FUEL CO., LTD.

Inventor： Yong Kyoon MOK ,  Yoon Ho KIM ,  Tae Sik JUNG ,  Sung Yong LEE ,  Hun JANG ,  Chung Yong LEE ,  Yeon Soo NA ,  Min Young CHOI ,  Dae Gyun KO ,  Seung Jae LEE ,  Jae Ik KIM

IPC: C22F1/18 ,  C22C16/00 ,  C22F1/00 ,  G21C3/07

CPC classification number: C22F1/186 ,  B21B3/00 ,  B21B37/16 ,  C22C16/00 ,  C22F1/002 ,  C22F1/18 ,  G21C3/07 ,  G21C21/00

Abstract: Disclosed is a method of manufacturing a zirconium alloy plate, wherein fine precipitates having an average size of 35 nm or less are uniformly distributed in a matrix through multi-pass hot rolling, thus increasing corrosion resistance and fatigue failure resistance, the method including forming a zirconium alloy ingot (step 1); subjecting the ingot of step 1 to beta annealing and rapid cooling (step 2); preheating the ingot of step 2 (step 3); forming a multi-pass hot-rolled plate through primary hot rolling and then air cooling during which secondary hot rolling is subsequently conducted (step 4); subjecting the multi-pass hot-rolled plate of step 4 to primary intermediate annealing and primary cold rolling (step 5); subjecting the rolled plate of step 5 to secondary intermediate annealing and secondary cold rolling (step 6); subjecting the rolled plate of step 6 to tertiary intermediate annealing and tertiary cold rolling (step 7); and finally annealing the rolled plate of step 7 (step 8).

公开(公告)号：US09659675B2

公开(公告)日：2017-05-23

申请号：US14149872

申请日：2014-01-08

Applicant: KEPCO NUCLEAR FUEL CO., LTD.

Inventor： Ju Young Lee ,  Chang Hwan Hwang ,  Hung Soon Chang ,  Soon Ki Guk ,  Yeon Doo Jung ,  Ui Jea Lee

IPC: G21C3/334 ,  G21C21/00 ,  G21C19/32

CPC classification number: G21C19/32 ,  G21C3/334 ,  G21C21/00 ,  Y02E30/40

Abstract: Disclosed is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit.

公开(公告)号：US09496058B2

公开(公告)日：2016-11-15

申请号：US14543286

申请日：2014-11-17

Applicant: Wayne Marquino ,  Stephan C. Moen ,  Richard M. Wachowiak ,  John L. Gels ,  Jesus Diaz-Quiroz ,  John C. Burns, Jr.

Inventor： Wayne Marquino ,  Stephan C. Moen ,  Richard M. Wachowiak ,  John L. Gels ,  Jesus Diaz-Quiroz ,  John C. Burns, Jr.

IPC: G21C19/303 ,  G21C9/06 ,  G21C19/317 ,  B01J12/00 ,  G21C21/00 ,  B01D53/86 ,  B01J23/40 ,  B01J35/04

CPC classification number: G21C19/303 ,  B01D53/8671 ,  B01D2255/1023 ,  B01D2255/1025 ,  B01D2257/108 ,  B01J12/007 ,  B01J23/40 ,  B01J35/04 ,  G21C9/06 ,  G21C19/317 ,  G21C21/00 ,  Y02E30/40

Abstract: Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.

Abstract translation: 系统被动地从不受外部电力和/或移动部件需要的情况下，消除来自容易受到核能发电厂的不凝析气体（如H2和O2）的燃烧造成损害的设备的不凝气体。 系统包括安装在无源遏制冷却系统（PCCS）冷凝器的下集管中的催化剂板，催化剂填充构件和/或PCCS冷凝器的冷凝管的内表面上的催化剂涂层或PCCS的环形出口 冷凝器 结构可以具有抑制水形成并促进与不可冷凝气体接触的表面或疏水性元素。 通过单独或组合安装和使用系统来消除核电厂中不凝气体。 可以增加PCCS冷凝器的操作压力以促进其中不凝结气体的复合。

公开(公告)号：US20160232991A1

公开(公告)日：2016-08-11

申请号：US15022536

申请日：2014-09-16

Applicant: CZECH TECHNICAL UNIVERSITY IN PRAGUE, FACULTY OF M ECHANICAL ENGINEERING, DEPARTMENT OF ENERGY ENGIE ,  INSTITUTE OF PHYSICS OF THE ACADEMY OF SCIENCES OF THE CZECH REPUBLIC, V.V.I.

Inventor： Radek SKODA ,  Jan SKAROHLID ,  Irena KRATOCHVILOVA ,  Frantisek FENDRYCH ,  Andrew James TAYLOR

IPC: G21C3/07 ,  G21C3/34 ,  C23C16/27

CPC classification number: G21C3/07 ,  C23C16/27 ,  G21C3/34 ,  G21C17/0225 ,  G21C21/00

Abstract: A layer protecting the surface of zirconium alloys used as materials for nuclear reactors is formed by a homogenous polycrystalline diamond layer prepared by chemical vapor deposition method. This diamond layer is 100 nm to 50 μm thick and the size of the crystalline cores in the layer ranges from 10 nm to 500 nm. Maximum content of non-diamond carbon is 25 mol %, total content of non-carbon impurities is maximum up to 0.5 mol %, RMS surface roughness of the polycrystalline diamond layer has a value less than 40 nm and thermal conductivity of the layer ranges from 1000 to 1900 W⊙m−1⊙⊙K−1. Coating of the zirconium alloys surface with the described polycrystalline diamond layer serves as a zirconium alloys surface protection against undesirable changes and processes in the nuclear reactor environment.

Abstract translation: 通过化学气相沉积法制备的均质多晶金刚石层形成了保护用作核反应堆材料的锆合金表面的层。 该金刚石层的厚度为100nm〜50μm，层内的晶核尺寸为10nm〜500nm。 非金刚石碳的最大含量为25mol％，非碳杂质的总含量最高达0.5mol％，多晶金刚石层的RMS表面粗糙度小于40nm，该层的热导率范围为 1000〜1900W⊙m-1⊙⊙K-1。 用所述的多晶金刚石层涂覆锆合金表面起到锆合金表面保护作用，防止核反应堆环境中的不希望的变化和过程。

公开(公告)号：US09236151B2

公开(公告)日：2016-01-12

申请号：US13564281

申请日：2012-08-01

Applicant: Christophe Lorrette ,  Daniel Nunes ,  Cédric Sauder

Inventor： Christophe Lorrette ,  Daniel Nunes ,  Cédric Sauder

IPC: B21F9/00 ,  B66F3/00 ,  G21C3/06 ,  C04B35/52 ,  C04B35/565 ,  C04B35/80 ,  C04B35/83 ,  G21C21/00

CPC classification number: G21C3/06 ,  C04B35/52 ,  C04B35/565 ,  C04B35/806 ,  C04B35/83 ,  C04B2235/5244 ,  C04B2235/5248 ,  C04B2235/5252 ,  C04B2235/614 ,  C04B2235/94 ,  G21C21/00 ,  Y02E30/40

Abstract: A device for tensioning a preform made from interlaced fibers is applied to tension the preform used in a process for fabricating a part made from a ceramic matrix composite material. During this process, the preform is tensioned before and during its densification using the tensioning device (100), which comprises a main body (2), a first assembly element (3) and a second assembly element (4) and a control rod, rotation of the control rod causing translation of the second assembly element, separation of the first and second assembly elements from each other and tensioning of the preform along the longitudinal direction.

Abstract translation: 施加用于张紧由隔行纤维制成的预成型件的装置，用于张紧用于制造由陶瓷基复合材料制成的部件的工艺中的预成型件。 在该过程中，使用包括主体（2），第一组件元件（3）和第二组件元件（4）以及控制杆的张紧装置（100），在其致密化之前和期间使预成型件张紧， 所述控制杆的旋转导致所述第二组装元件的平移，所述第一和第二组件元件彼此分离并且沿着所述纵向方向张紧所述预成型件。