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1. 发明申请

US20210343432A1 INTEGRAL REACTOR PRESSURE VESSEL TUBE SHEET 有权
公开(公告)号：US20210343432A1
公开(公告)日：2021-11-04
申请号：US17351213
申请日：2021-06-17
申请人： NuScale Power, LLC
发明人： Tamas Liszkai , Seth Cadell , Alex Kruskamp , Matthew Mallet
IPC分类号： G21C15/12 , G21C13/02 , G21C15/16
摘要： A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.

2. 发明申请

US20210193339A1 INTEGRATED PASSIVE COOLING CONTAINMENT STRUCTURE FOR A NUCLEAR REACTOR 有权
公开(公告)号：US20210193339A1
公开(公告)日：2021-06-24
申请号：US16726359
申请日：2019-12-24
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： David H. Hinds
IPC分类号： G21C15/12 , G21C13/028 , G21C13/093 , E04H7/18
摘要： An integrated passive cooling containment structure for a nuclear reactor includes a concentric arrangement of an inner steel cylindrical shell and an outer steel cylindrical shell that define both a lateral boundary of a containment environment of the nuclear reactor that is configured to accommodate a nuclear reactor and an annular gap space between the inner and outer steel cylindrical shells, a concrete donut structure at a bottom of the annular gap space, and a plurality of concrete columns spaced apart azimuthally around a circumference of the annular gap and extending in parallel from a top surface of the concrete donut structure to a top of the annular gap space. The outer and inner steel cylindrical shells and the concrete donut structure at least partially define one or more coolant channels extending through the annular gap space.

3. 发明申请

US20210174977A1 PASSIVE INFINITE COOLING STRUCTURE FOR NUCLEAR REACTOR AND METHOD OF OPERATING THE SAME 有权
公开(公告)号：US20210174977A1
公开(公告)日：2021-06-10
申请号：US17008809
申请日：2020-09-01
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Sung-Jae YI , Hyun Sik PARK
IPC分类号： G21C15/26 , G21C15/12
摘要： The present invention relates to a passive infinite cooling system for a nuclear reactor and a method of operating the same. The system includes an energy release space in which a reactor vessel is accommodated, an energy absorbing space separated from the energy release space, an energy transfer space, which is provided above the energy absorbing space, absorbs and cools heat transferred from the reactor vessel, and discharges the absorbed heat to the outside through an outer wall thereof, a first cooling flow path through which the heat in the reactor vessel is transferred to the energy transfer space, a pressure balance pipe through which the pressure in the energy release space is transferred to the energy absorbing space, and a coolant spray pipe through which the cooling water in the energy absorbing space pressurized by the pressure balance pipe is transferred to the energy transfer space. The energy transfer space includes a saturated vapor pressure cooling chamber, which is formed to be connected to an inner side of an upper outer wall of the cooling space, and in which cooling water is accommodated, a heat exchanger of the first cooling flow path is located, and a spray-side end of the coolant spray pipe is located, and a reference atmospheric pressure chamber, which is provided below the saturated vapor pressure cooling chamber and communicates with the saturated vapor pressure cooling chamber, is filled with air so as to achieve a pressure balance with the cooling water in the saturated vapor pressure cooling chamber, and in which a water level thereof varies according to a pressure in the saturated vapor pressure cooling chamber.

4. 发明申请

US20210134471A1 Nuclear reactor and nuclear reactor vessel equipped with non-ejectable valve 有权
公开(公告)号：US20210134471A1
公开(公告)日：2021-05-06
申请号：US17055407
申请日：2019-05-16
申请人： Société Technique pour l'Energie Atomique
发明人： Laurent CANDILLIER , Michel BRUN
IPC分类号： G21C11/08 , G21C13/036 , G21C15/12
摘要： A nuclear reactor vessel includes a shell (5) having a wall (9) traversed by at least one passage (11) having a central axis (C) and a valve (21) mounted in the passage (11), the valve (21) having a determined outer cross-section. The passage (11) has an inner end segment (23) that opens into the inner volume (7) and an outer end segment (25) that opens into an outer piping (13), the valve (21) being housed in the inner end segment (23). The valve (21) is capable of being extracted from the passage (11) through the inside of the vessel (1). The outer end segment (25) has at least one portion having an inner cross-section, perpendicular to the central axis (C), that is smaller than the outer cross-section of the valve (21), such that the valve (21) cannot be ejected out of the vessel (1).

5. 发明申请

US20210012913A1 LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM 有权
公开(公告)号：US20210012913A1
公开(公告)日：2021-01-14
申请号：US16883592
申请日：2020-05-26
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , Joseph Rajkumar
IPC分类号： G21C15/18 , G21C13/02 , G21C15/12 , G21D1/00
摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

6. 发明申请

US20190148027A1 INTEGRATED SYSTEM FOR CONVERTING NUCLEAR ENERGY INTO ELECTRICAL, MECHANICAL, AND THERMAL ENERGY AND METHODS FOR USING THE SAME 审中-公开
公开(公告)号：US20190148027A1
公开(公告)日：2019-05-16
申请号：US15809652
申请日：2017-11-10
申请人： NuGen, LLC
发明人： Stephen K. RHYNE , Pavel V. TSVETKOV
IPC分类号： G21D5/02 , G21D1/02 , G21C13/024 , G21C15/253 , G21C15/12 , F02C1/05
摘要： Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

7. 发明授权

US10249397B2 Modular reactor steam generator configured to cover a reactor outer wall circumference 有权
公开(公告)号：US10249397B2
公开(公告)日：2019-04-02
申请号：US15445376
申请日：2017-02-28
申请人： KEPCO ENGINEERING & CONSTRUCTION COMPANY, INC.
发明人： Sung Ho Park , Jong Min Kim , Kyu Wan Kim
IPC分类号： G21D1/00 , F22B21/04 , G21C15/12 , F16T1/00 , G21C1/32 , G21C15/16
摘要： In an externally integrated steam generator type small modular reactor, a steam generator is arranged along the circumference of a reactor vessel cylindrical shell, and a steam drum is arranged along the circumference of the steam generator. The small modular reactor includes: a nuclear reactor including a hemispherical upper head, the reactor vessel cylindrical shell coupled to the upper head and extending downward from the upper head in a cylindrical shape, and a hemispherical lower head provided on a lower portion of the reactor vessel cylindrical shell, wherein a core is placed in the nuclear reactor; the steam generator surrounding all around the reactor vessel cylindrical shell and including a first penetration hole communicating with an inside of the nuclear reactor; and the steam drum surrounding the circumference of the steam generator and including a second penetration hole communicating with an inside of the steam generator.

8. 发明申请

US20180033500A1 EXTERNALLY INTEGRATED ONCE-THROUGH STEAM GENERATOR TYPE SMALL MODULAR REACTOR 审中-公开
公开(公告)号：US20180033500A1
公开(公告)日：2018-02-01
申请号：US15445394
申请日：2017-02-28
申请人： KEPCO ENGINEERING & CONSTRUCTION COMPANY, INC.
发明人： Sung Ho PARK , Jong Min Kim , Kyu Wan Kim
IPC分类号： G21C15/12
CPC分类号： G21C15/12 , F16T1/00 , F22B1/00 , G21C1/09 , G21C1/32 , G21C13/02 , G21C15/243 , G21D1/006 , Y02E30/40
摘要： In an externally integrated once-through steam generator type small modular reactor, a steam generator is arranged along the circumference of a reactor vessel, and secondary cooling water flows in heat transfer tubes and changes to superheated steam. The small modular reactor includes: a nuclear reactor including a hemispherical upper head, the reactor vessel cylindrical shell coupled to the upper head and extending downward from the upper head in a cylindrical shape, and a hemispherical lower head provided on a lower portion of the reactor vessel cylindrical shell, wherein a core is placed in the nuclear reactor; the steam generator surrounding all around the reactor vessel cylindrical shell, the steam generator including a first penetration hole communicating with an inside of the nuclear reactor and a second penetration hole separate from the first penetration hole and communicating with the inside of the nuclear reactor.

9. 发明授权

US09773574B2 Systems and methods for enhancing isolation of high-temperature reactor containments 有权
公开(公告)号：US09773574B2
公开(公告)日：2017-09-26
申请号：US14533055
申请日：2014-11-04
申请人： THE REGENTS OF THE UNIVERSITY OF CALIFORNIA
发明人： Per F. Peterson
IPC分类号： G21C1/04 , G21C11/08 , G21C13/02 , G21C13/10 , G21C15/12 , G21C15/18
CPC分类号： G21C11/08 , G21C13/02 , G21C13/10 , G21C15/12 , G21C15/18 , Y02E30/35
摘要： A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

10. 发明申请

US20170133112A1 NUCLEAR REACTOR SYSTEM HAVING NATURAL CIRCULATION OF PRIMARY COOLANT 审中-公开
公开(公告)号：US20170133112A1
公开(公告)日：2017-05-11
申请号：US15413770
申请日：2017-01-24
申请人： SMR Inventec, LLC
发明人： Krishna P. Singh , P. Stephan Anton , Ranga Nadig , Indresh Rampall
IPC分类号： G21C15/26 , G21C1/08 , G21D1/00 , G21C15/12 , G21C13/04
CPC分类号： G21C15/26 , G21C1/086 , G21C7/32 , G21C13/04 , G21C15/12 , G21D1/006 , Y02E30/32 , Y02E30/39
摘要： A nuclear reactor system that, in one embodiment, utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core and a heat exchange sub-system. The heat exchange subsystem is located outside of the nuclear reactor pressure vessels and, in some embodiments, is designed so as to not cause any substantial pressure drop in the flow of the primary coolant within the heat exchange sub-system that is used to vaporize a secondary coolant in another embodiment, a nuclear reactor system is disclosed in which the reactor core is located below ground and all penetrations into the reactor pressure vessel are located above ground.

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