公开(公告)号：US20240363259A1

公开(公告)日：2024-10-31

申请号：US18681816

申请日：2022-08-11

Applicant: Kernkraftwerk Gösgen-Däniken AG

Inventor： Rainer KAULBARSCH ,  Fabian JATUFF ,  Stefano CARUSO ,  Leo ORNOT ,  Marcel RIEKER ,  Davide PAPINI

IPC: G21C17/06 ,  G01K17/08

CPC classification number: G21C17/06 ,  G01K17/08

Abstract: A device for the calorimetric determination of the decay heat power of fuel elements has a calorimeter container with a coolant inlet and a coolant outlet, a line system with a coolant removal line and a coolant supply line, a feed pump, a flow measuring device, a first temperature measuring device at the coolant inlet, a second temperature measuring device at the coolant outlet, and a closing cover.

公开(公告)号：US20240347220A1

公开(公告)日：2024-10-17

申请号：US18431787

申请日：2024-02-02

Applicant: Westinghouse Electric Company LLC

Inventor： James T. Polidora ,  Shawn D. Lazeski ,  Jeff H. Sleasman

IPC: G21C17/06 ,  G01L19/08 ,  G21C19/07 ,  G21C19/10 ,  G21C19/20 ,  H04N5/77 ,  H04N23/50

CPC classification number: G21C17/06 ,  G01L19/086 ,  G21C19/10 ,  H04N5/77 ,  G21C19/07 ,  G21C19/207 ,  H04N23/555

Abstract: A fuel assembly inspection system that utilizes a pressure transducer mounted to a utility's spent fuel handling tool to detect a relative change in depth of a fuel assembly during fuel inspections. The system then wirelessly transmits the signal to a fuel inspection recording system, which converts the signal to a relative height along the fuel assembly being viewed by a camera, and displays the relative height along with the applicable fuel assembly feature being viewed by the camera (e.g., nozzle, grid, span) via a text overlay on the video image of the inspection.

公开(公告)号：US20240221966A1

公开(公告)日：2024-07-04

申请号：US18608909

申请日：2024-03-18

Applicant: Xi'an Jiaotong University

Inventor： Di Yun ,  Yiwei Zhao ,  Jie Qiu ,  Yi Le ,  Haibin Mu ,  Yijia Luo ,  Xinlu Gu ,  Shuang Xiang ,  Wenbo Liu

IPC: G21F5/10 ,  G21C17/06

CPC classification number: G21F5/10 ,  G21C17/06

Abstract: The present disclosure provides a method for pre-separating nuclides in spent fuel, comprising steps: S1. generating a temperature of 1200 to 1600° C. in a center of a fuel element, and at the same time introducing a cooling medium to an outer surface of the fuel element, to introduce a temperature difference to heat the fuel element; S2. soaking cooled spent fuel in an ionic liquid to selectively dissolve fission products and transuranic elements, so that the fission products and the transuranic elements are pre-separated from the spent fuel. The method achieves the effect of pre-separating part of the fission products and transuranic elements by physical methods, and solves the problem that homogenization in traditional post-processing technology causes obstacles to nuclide separation.

公开(公告)号：US20230268090A1

公开(公告)日：2023-08-24

申请号：US17679784

申请日：2022-02-24

Applicant: GE-Hitachi Nuclear Energy Americas LLC

Inventor： Kevin D. WATTS ,  Hubert H. HUIE ,  Aimee Lee LAVIGNE ,  Vincent Carl VIGLIANO ,  Mary Bodar CALLAHAN

IPC: G21C17/06 ,  G01T1/16

CPC classification number: G21C17/06 ,  G01T1/16

Abstract: A method of measuring moisture carryover (MCO) in a nuclear reactor includes placing a first gamma detector adjacent to a steam conduit configured to transport steam generated by the core. The method additionally includes detecting a first amount of carryover gamma activity of a first quantity of sodium-24 in the steam within the steam conduit with the first gamma detector. The method also includes detecting a second amount of reference gamma activity of a second quantity of sodium-24 in a reference sample of reactor water from the core with a second gamma detector. The method further includes determining a flow rate of liquid water entrained in the steam based on the first amount of carryover gamma activity detected by the first gamma detector and the second amount of reference gamma activity detected by the second gamma detector.

公开(公告)号：US20180075933A1

公开(公告)日：2018-03-15

申请号：US15703655

申请日：2017-09-13

Applicant: Battelle Energy Alliance, LLC

Inventor： Ahmad Y Al Rashdan

IPC: G21C17/06 ,  G21F5/06 ,  G01T1/167

CPC classification number: G21C17/06 ,  G01M3/38 ,  G01T1/167 ,  G08C2201/10 ,  G21F5/06 ,  G21F5/10 ,  G21F5/12 ,  G21F5/125 ,  H02J7/0055 ,  H04Q9/00

Abstract: A method and apparatus for online condition monitoring of a spent nuclear fuel dry cask storage system. The method comprises monitoring physical parameters of air flowing through inlet vents and outlet vents of a system and observing successive measurements of the parameter for deviations from the baseline to determine if the condition of the system has changed. The parameters may include temperature, pressure, density, mass and volumetric flow rate, nuclear radiation, impurities, humidity, salt content, acidity, chemistry, and fission product gases. The information may then be used directly or to develop an accumulation profile. The data may also be used in modeling or other simulations and to establish condition change signatures. The apparatus includes sensors placed over inlet and outlet vents, sensor interfacing hardware connected to the sensors, and a computer connected to the hardware to acquire, display, and analyze the sensor data and to display the status of the system.

公开(公告)号：US09733074B2

公开(公告)日：2017-08-15

申请号：US14452300

申请日：2014-08-05

Applicant: COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

Inventor： Laurent Loubet ,  Brigitte Lacroix ,  Jean Noirot ,  Thierry Martella

IPC: G01B15/06 ,  G01T1/36 ,  G21C17/06

CPC classification number: G01B15/06 ,  G01T1/36 ,  G21C17/06

Abstract: A method for analysing at least one fuel rod comprising a stack of nuclear fuel, a rod comprising packed zones completely filled with fuel and intermediate zones partially full of fuel, comprises: acquiring a count profile associated with a non-migrating isotope, a profile being made up of spectrometry measurements taken along the rod for this isotope; determining a set of at least one indicator K_i that makes it possible to quantify the reduction in material at an intermediate zone of index i, the said indicator being deduced from the count profile; detecting the change in geometry by comparing the set of at least one indicator K_i against a set of at least one reference value RK indicative of the initial geometry of the nuclear fuel stack.

公开(公告)号：US20170194064A1

公开(公告)日：2017-07-06

申请号：US14985537

申请日：2015-12-31

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： JAMES T. POLIDORA ,  SHAWN D. LAZESKI ,  JOHN W. CONRAD

IPC: G21C17/10 ,  G21C1/08

CPC classification number: G21C17/10 ,  G21C1/086 ,  G21C3/334 ,  G21C3/356 ,  G21C17/06 ,  Y02E30/40

Abstract: An improved measurement apparatus employs a support that includes a housing and that further includes a follower that is movably situated on the support. The follower is biased in a direction generally away from the housing. The housing and follower are receivable between a spring/dimple pair, and a sensor detects the distance between the housing and the follower when interposed between the spring and dimple. An indicator apparatus employs the signal to output and indication that is representative of the amount of compressive loading that will be applied to a fuel rod by the spring/dimple pair, and the indication is based at least in part upon the distance between the portion of the housing that is engaged with the dimple and the portion of the follower that is engaged with the spring.

公开(公告)号：US09530527B2

公开(公告)日：2016-12-27

申请号：US12841848

申请日：2010-07-22

Applicant: Mihai G. M. Pop ,  Anthony A. Pugh ,  Laurence S. Lamanna ,  John T. Willse

Inventor： Mihai G. M. Pop ,  Anthony A. Pugh ,  Laurence S. Lamanna ,  John T. Willse

IPC: G01C17/00 ,  G21C17/017 ,  G21C17/06 ,  G21C19/00 ,  G01N23/225 ,  G01N1/04 ,  G01N1/02

CPC classification number: G21C17/017 ,  G01N1/04 ,  G01N23/225 ,  G01N2001/028 ,  G01N2223/625 ,  G21C17/06 ,  G21C19/00

Abstract: A method to perform an analysis of two types of CRUD on a nuclear fuel rod, including providing a nuclear fuel rod with a first and second layer of CRUD on an exterior of the fuel rod; brushing the first layer of CRUD from the fuel rod with a CRUD tool on a selected area; wherein the tool has a brushing device, a force applied to the brushing device on the fuel rod to remove the first layer of CRUD, the force being sufficient enough to perform such removal; collecting the first layer of CRUD from the brushing device, scraping the second layer of CRUD from the fuel rod in the selected area with the tool, wherein the tool has a scraping device and a second force is applied to the tool for scraping, collecting the second layer of CRUD from the scraping device, and analyzing the first layer and second layer of CRUD separately with a scanning electron microscope.

Abstract translation: 在核燃料棒上执行两种类型的CRUD分析的方法，包括在燃料棒的外部提供具有第一和第二层CRUD的核燃料棒; 使用选定区域上的CRUD工具从燃料棒上刷第一层CRUD; 其中所述工具具有刷洗装置，施加到所述燃料棒上的所述刷洗装置上以除去所述第一CRUD层的力，所述力足以足以执行所述移除; 从刷洗装置收集第一层CRUD，用工具从选定区域中的燃料棒刮取第二层CRUD，其中该工具具有刮削装置，并且第二力施加到该工具上用于刮擦，收集 第二层CRUD，并用扫描电子显微镜分别分析第一层和第二层CRUD。

公开(公告)号：US20160012925A1

公开(公告)日：2016-01-14

申请号：US14791270

申请日：2015-07-03

Applicant: Ahlberg Cameras AB

Inventor： Joakim AHLBERG

IPC: G21C17/08

CPC classification number: G21C17/06 ,  G21D3/001 ,  Y02E30/40

Abstract: A method, system and computer program product for measuring a spatial displacement of at least a part of an irradiating nuclear fuel assembly. The system comprising a memory and a processor configured to receive data from said memory. The processor and the computer program being configured to: receive a first image data frame, captured using an imaging system, said first image data frame comprising information representing a first view of an observed real world scene comprising at least a part of a fuel assembly, wherein said first image data frame is captured from a first direction; generate a set of reference coordinates, corresponding to image coordinates of said first image data frame; and extract measurement data indicative of a spatial displacement relating to at least a part of said fuel assembly, based on information from said first image data frame and information from said set of reference coordinates.

Abstract translation: 一种用于测量照射核燃料组件的至少一部分的空间位移的方法，系统和计算机程序产品。 所述系统包括存储器和被配置为从所述存储器接收数据的处理器。 处理器和计算机程序被配置为：接收使用成像系统捕获的第一图像数据帧，所述第一图像数据帧包括表示包括燃料组件的至少一部分的观察到的真实世界场景的第一视图的信息， 其中所述第一图像数据帧从第一方向被捕获; 生成对应于所述第一图像数据帧的图像坐标的一组参考坐标; 并且基于来自所述第一图像数据帧的信息和来自所述参考坐标系的信息，提取指示与所述燃料组件的至少一部分有关的空间位移的测量数据。

公开(公告)号：US09134433B2

公开(公告)日：2015-09-15

申请号：US13814369

申请日：2011-08-09

Applicant: Takao Nishimura ,  Kenichiro Kino

Inventor： Takao Nishimura ,  Kenichiro Kino

IPC: G01T1/178 ,  G21C17/04 ,  G01T1/167 ,  G21C17/02 ,  G01T7/02 ,  G21C17/06 ,  G21C1/02

CPC classification number: G01T1/167 ,  G01T7/02 ,  G21C1/022 ,  G21C17/02 ,  G21C17/022 ,  G21C17/06

Abstract: A nuclear reactor fuel integrity monitor includes: a γ-ray detector which detects γ-ray of a specific radionuclide of a subject measurement medium of a nuclear reactor; a sample container which retains the subject measurement medium therein and surrounds the circumference of the γ-ray detector; and a measurement control device which performs a control so that a predetermined amount of the subject measurement medium is introduced into the sample container and calculates a concentration of the specific radionuclide from γ-ray data per each unit time detected by the γ-ray detector and a volume of the subject measurement medium introduced into the sample container.

Abstract translation: 核反应堆燃料完整性监视器包括：γ射线检测器，其检测核反应堆的被测量介质的特定放射性核素的γ射线; 样本容器，其将被检测体介质保持在其中并且包围γ射线检测器的周围; 以及测量控制装置，其进行控制，使得将预定量的被摄体测量介质引入到样本容器中，并根据由γ射线检测器检测的每单位时间的γ射线数据计算特定放射性核素的浓度;以及 将被测量介质的体积引入到样品容器中。