Tsinghua University

Chinergy Co., Ltd.

Yujie Dong

Zuoyi Zhang

Xin Wang

Haiquan Zhang

Hongke Li

Junfeng Nie

Fu Li

Jiguo Liu

Bing Liu

Haitao Wang

Yu Wang

Yue Li

Lei Wang

Bin Wu

He Yan

Jinhua Wang

Bing Xia

Zongxin Wu

Xingzhong Diao

Liguo Zhang

Yuliang Sun

Yuanhui Xu

Zhichun Fan

Dazhong Wang

Jianzhu Cao

Jiejuan Tong

Jiong Guo

The present disclosure relates to a method for monitoring failure of coated particles in fuel elements in a core of a pebble-bed high-temperature gas-cooled reactor, which is related to the technical field of nuclear reactor engineering and includes the following steps: S, calculating an inventory of a short-lived noble gas fission nuclide; S, obtaining a ratio of a release rate to a birth rate of the short-lived noble gas fission nuclide based on a temperature of the fuel elements using a Booth diffusion and release model; S, deriving a theoretical expression for an activity concentration of the short-lived noble gas fission nuclide in a primary circuit using a migration model of the nuclide in the primary circuit; S, obtaining an experimental measurement value of the activity concentration of the short-lived noble gas fission nuclide in the primary circuit at a sampling moment by gas sampling; S, optimally calculating a failure fraction of the coated particles in the fuel elements and a share of uranium contamination in the matrix graphite in the core based on the theoretical expression and the experimental measurement value. The present disclosure can provide key parameters for the performance and status of the fuel elements in the core, which are required for radiation safety studies, source term calculations and accident analysis of the pebble-bed high-temperature gas-cooled reactor.

Method for monitoring failure of coated particles in fuel elements in core of pebble-bed high-temperature gas-cooled reactor

Multiple groups of nuclear fuel storage containers can be put into the nuclear fuel transport container provided by the present application as a whole to realize the overall transportation of the multiple groups of storage containers; the transport container has a cubic structure in appearance, which can fully utilize the transportation space and improve the transportation efficiency; an outer side of the transport container is provided with an anti-penetration structure, which can effectively alleviate the collision and penetration damage caused by transportation and hoisting accident, and ensure that the nuclear fuel element can be safely enclosed after the accident; heat insulation material is provided between inner and outer steel plates of the transport container, which can effectively protect the internal storage container and the loaded nuclear fuel element under fire condition, and the heat insulation material also has a function of drop buffer.

Method and equipment for transporting nuclear fuel of nuclear power plant

The present application relates to the field of mechanical engineering technologies, and particularly to an unloading device. The unloading device includes a power mechanism, a transmission mechanism, and an execution mechanism that are connected in sequence from top to bottom; wherein the execution mechanism includes a shafting assembly and a turntable assembly that are connected in sequence from top to bottom; wherein the turntable assembly includes an upper auxiliary fence, a middle main disturbance disk, and a lower reclaiming portion that are arranged in sequence from top to bottom. The unloading device provided by the present application is easy to control, and ensures the reclaiming reliability of the spherical materials and the stability of the sphere flow unloading, which can meet the requirements of long life and reliable operation of the unloading device under light load and low speed working conditions and achieve the convenient maintenance.

Unloading device

The present application relates to an unloading and temporary storage device. The unloading and temporary storage device includes a stock bin, a stock bin external member, a stock bin internal member, a shielding module and a loading module; the stock bin includes a barrel and a tank body; the stock bin external member includes a cooling water jacket; the stock bin internal member includes a straight bin, an inclined bin and an unloading bin that communicate sequentially; the shielding module includes an external shield and a neutron shield; the loading module includes a loading body; and sphere inlet passages are provided in the loading body. The unloading and temporary storage device can perform the functions of receiving, temporarily storing, atmosphere switching, and unloading of spherical elements, and also has the safety functions of ensuring geometrical integrity of the spherical elements, radiological protection and residual heat removal.

Unloading and temporary storage device

The present application relates to a spherical object falling buffer device including a flow-limiting pipe assembly and a central column assembly; wherein the flow-limiting pipe assembly includes a flow-limiting pipe, a redirecting joint and a sphere outlet pipe; a diameter of the flow-limiting pipe is greater than that of the sphere outlet pipe, and an inner surface of the redirecting joint is a conical surface; the central column assembly includes at least a central column arranged in the flow-limiting pipe; a flow-guiding region is provided between the flow-limiting pipe and the central column, and a plurality of gravity flow guide grooves are provided on an outer peripheral surface of the central column. The spherical object falling buffer device may restrict, guide and buffer spherical objects during falling, and avoids collision damage of the spherical objects or the stock bin due to the excessive falling speed of the spherical objects.

Spherical object falling buffer device

The present disclosure relates to the field of reactor engineering technologies, and particularly to a spherical element detecting and positioning device. The spherical element detecting and positioning device includes a pressure-bearing casing, an internal member and an execution part; the pressure-bearing casing includes a tank body, one sphere inlet adapter pipe and two sphere outlet adapter pipe respectively arranged on the tank body; the internal member is arranged in the rotor counter-bored hole and includes a lining ring and a limit ring; and the execution part includes a turntable and two support lugs. The spherical element detecting and positioning device provided by the present disclosure can achieve triple functions of performing automatic material separation, precise positioning and directional conveyance of spherical elements, has compact structure and simple control, and can meet the operation reliability and maintainability requirements for long-term and intermittent operation under the strong radioactive environment.

Spherical element detecting and positioning device for a pebble bed nuclear reactor

Disclosed are an electrical penetration assembly, a manufacturing method thereof, and an electrical penetration device, which relate to the technical field of electrical penetration. The electrical penetration assembly comprises sealing glass (), an outer tube () and a conductor () inserted into the outer tube (), wherein both ends of the outer tube () are blocked by supporting and fixing blocks (), and both ends of the conductor () respectively protrude from the corresponding supporting and fixing blocks (); the sealing glass () is sintered between the conductor () and the outer tube () and is configured to divide an annular cavity jointly enclosed by the conductor (), the outer tube () and the supporting and fixing blocks () into an upper cavity and a lower cavity; an optical fiber () penetrates the sealing glass (), at least one end of the optical fiber () is connected to an optical fiber splice () after protruding from the corresponding supporting and fixing block (), and a portion of the optical fiber () located in the sealing glass () is inscribed with a fiber Bragg grating to form a first fiber Bragg grating sensor (). By utilizing the first fiber Bragg grating sensor () to monitor the strain and temperature of the sealing glass () in real time, not only can it judge whether the electrical penetration assembly meets the requirements for hermeticity, but also enable precise control of the sintering temperature.

Electrical penetration assembly, manufacturing method thereof, and electrical penetration device

A high-temperature gas-cooled reactor steam generating system comprises a plurality of nuclear steam supply systems, a high-pressure cylinder (), a low-pressure cylinder (), a condenser (), a condensate pump (), a low-pressure heater (), a deaerator (), a water supply pump (), and a high-pressure heater () which are sequentially connected end to end to form a close steam loop. On one hand, the inherent safety of the reactor is guaranteed and the generating system is simplified with the inherent safety. On the other hand, the scale economy of the steam engine system and other systems of a whole power station is guaranteed through batch copy, a shared auxiliary system and a scale effect.

High-temperature gas-cooled reactor steam generating system and method

Growing community of inventors

Beijing, China

Yujie Dong