公开(公告)号：US11913465B2

公开(公告)日：2024-02-27

申请号：US16971874

申请日：2019-02-21

申请人： CANDU ENERGY INC.

发明人： Richard Dam

IPC分类号： F04D29/12 ,  F04D3/00 ,  F04D29/08 ,  F16J15/34 ,  G21C15/04 ,  G21C15/243 ,  F04D29/16

CPC分类号： F04D29/086 ,  F04D3/00 ,  F16J15/34 ,  F16J15/3408 ,  F16J15/3428 ,  G21C15/04 ,  G21C15/243 ,  F04D29/12 ,  F04D29/16

摘要： A seal assembly for a pump comprises a gland housing mounted to the pump casing. A staging flow pathway is defined within the gland housing with multiple seal chambers. A seal stage is positioned in each seal chamber, each having a static sealing element and a rotating sealing element, the sealing elements engaging one another to form a fluid-tight seal. A rotor assembly pumps coolant through the gland housing. Fluid passing through the staging flow pathway is accelerated by an acceleration surface of the rotor assembly. An inlet passage feeds coolant fluid into the staging flow pathway and past the acceleration surface.

公开(公告)号：US11901088B2

公开(公告)日：2024-02-13

申请号：US17088815

申请日：2020-11-04

申请人： SMR Inventec, LLC

发明人： Krishna P. Singh ,  Joseph Gerald Leo Rajkumar

IPC分类号： G21C15/243 ,  G21C7/32 ,  G21C15/26 ,  G21D1/00 ,  G21C13/073

CPC分类号： G21C15/243 ,  G21C7/32 ,  G21C15/26 ,  G21C13/073 ,  G21D1/00 ,  G21D1/006 ,  Y02E30/30

摘要： A method for heating primary coolant in a nuclear reactor system during system start-up. A primary coolant loop fluidly couples together a reactor vessel and a steam generating vessel. The primary coolant loop is filled with primary coolant. A portion of the primary coolant is taken from the primary coolant loop and placed into a start-up sub-system. The portion is heated while in the sub-system to form a heated portion of the primary coolant. The heated portion is returned into the primary coolant loop. The method allows for the primary coolant to be heated to a no-load operating temperature.

公开(公告)号：US11879689B1

公开(公告)日：2024-01-23

申请号：US17696491

申请日：2022-03-16

申请人： Triad National Security, LLC

发明人： Robert S. Reid ,  Robert A. Zimmerman ,  Cody M. Williams ,  Morgan T. Biel ,  Stephen J. Obrey ,  Todd A. Jankowski ,  Justin Simpson ,  Martin J. Ward ,  Lydia Wermer

IPC分类号： F28D15/04 ,  F28D15/02 ,  G21C15/02 ,  G21C15/257 ,  G21C15/243 ,  F28D21/00

CPC分类号： F28D15/043 ,  F28D15/0266 ,  F28D15/0275 ,  G21C15/02 ,  G21C15/243 ,  G21C15/257 ,  F28D2015/0216 ,  F28D2015/0291 ,  F28D2021/0054

摘要： A pump assisted heat pipe may combine the low mass flow rate required of latent heat pipe transfer loops with a hermetically sealed pump to overcome the typical heat pipe capillary limit. This may result in a device with substantially higher heat transfer capacity over conventional pumped single-phase loops, heat pipes, loop heat pipes, and capillary pumped loops with very modest power requirements to operate. Further, one or more embodiments overcome the gravitation limitations in the conventional heat pipe configuration, e.g., when the heat addition zone is above the heat rejection zone, the capillary forces are required to transfer the liquid from the heat rejection zone to the heat addition zone against gravity.

公开(公告)号：US20240006085A1

公开(公告)日：2024-01-04

申请号：US18368803

申请日：2023-09-15

申请人： Rolls-Royce North American Technologies Inc.

发明人： Daniel G. Edwards ,  Alexander Michalik ,  Andrew J. Eifert ,  Brian T. Spangler

IPC分类号： G21C15/12 ,  G21C15/253 ,  G21C15/243

CPC分类号： G21C15/12 ,  G21C15/253 ,  G21C15/243 ,  G21D3/00

摘要： A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

公开(公告)号：US11837370B2

公开(公告)日：2023-12-05

申请号：US17145743

申请日：2021-01-11

申请人： BWXT mPower, Inc.

发明人： Scott J. Shargots

IPC分类号： G21C15/24 ,  G21C1/32 ,  G21C1/09 ,  G21C15/243 ,  G21C1/08 ,  F04D13/10 ,  G21C21/00 ,  G21D1/04

CPC分类号： G21C1/32 ,  F04D13/10 ,  G21C1/086 ,  G21C1/09 ,  G21C15/24 ,  G21C15/243 ,  G21C21/00 ,  G21D1/04 ,  Y02E30/30 ,  Y10T29/49236 ,  Y10T29/49245

摘要： A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

公开(公告)号：US11545274B2

公开(公告)日：2023-01-03

申请号：US16582638

申请日：2019-09-25

申请人： GE-Hitachi Nuclear Energy Americas LLC

发明人： Derek Bass ,  Christer N. Dahlgren

IPC分类号： G21C19/307 ,  F22B35/00 ,  G21D1/00 ,  G21C15/243

摘要： Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

公开(公告)号：US20220277862A1

公开(公告)日：2022-09-01

申请号：US17145743

申请日：2021-01-11

申请人： BWXT mPower, Inc.

发明人： Scott J. Shargots

IPC分类号： G21C1/32 ,  G21C1/09 ,  G21C15/243 ,  G21C1/08 ,  F04D13/10 ,  G21C15/24 ,  G21C21/00 ,  G21D1/04

摘要： A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

公开(公告)号：US20220254526A1

公开(公告)日：2022-08-11

申请号：US17170233

申请日：2021-02-08

申请人： Rolls-Royce North American Technologies Inc.

发明人： Daniel G. Edwards ,  Alexander Michalik ,  Andrew J. Eifert ,  Brian T. Spangler

IPC分类号： G21C15/12 ,  G21C15/243 ,  G21C15/253

摘要： A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

公开(公告)号：US20210193340A1

公开(公告)日：2021-06-24

申请号：US17273536

申请日：2019-08-19

申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE ,  KING ABDULLAH CITY FOR ATOMIC AND RENEWABLE ENERGY

发明人： Kyungjun KANG ,  Jihan CHUN ,  Hanok KANG

IPC分类号： G21C15/16 ,  G21C15/12 ,  G21C15/243

摘要： Disclosed are a nuclear reactor long-term cooling system and a nuclear plant having the same. The nuclear reactor long-term cooling system, comprises: a lower containment area formed to enclose a reactor coolant system, and configured to prevent steam containing radioactive substances generated from the reactor coolant system from leaking to a path other than a discharge unit; an In-Containment Refueling Water Storage Tank (IRWST) disposed outside the lower containment area, and having refueling water stored therein; and a discharge pipe configured to connect the lower containment area to the IRWST, and to discharge steam of the lower containment area to the refueling water when an accident occurs. The nuclear plant may have an enhanced safety.

公开(公告)号：US10907668B2

公开(公告)日：2021-02-02

申请号：US15748365

申请日：2017-01-27

申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.

发明人： Masamichi Iino ,  Shigeto Hirai ,  Taiki Asahara ,  Takafumi Ogino ,  Akira Kirita ,  Akihiro Toda ,  Hideyuki Sakata ,  Yutaka Tanaka ,  Setsuo Tokunaga ,  Takashi Nakahara ,  Takanori Okazaki

IPC分类号： F15D1/00 ,  G21C15/18 ,  G21C15/243

摘要： A flow damper including a cylindrical vortex chamber, a small flow-rate pipe connected to a peripheral plate of the vortex chamber along a tangential direction, a large flow-rate pipe connected to the peripheral plate with a predetermined angle with respect to the small flow-rate pipe, an outlet pipe connected to an outlet formed in a central part of the vortex chamber, and a pressure equalization pipe with respective ends being connected to the peripheral plate on opposite sides of the outlet and at positions closer to a connection portion between the small flow-rate pipe and the large flow-rate pipe than positions facing each other, putting the outlet therebetween. The pressure equalization pipe is arranged with at least a part thereof is located at a higher position than a top plate of the vortex chamber, and an outgassing hole is provided at an uppermost part of the pressure equalization pipe.