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Passive activation safety device for nuclear reactor on abnormal dropping in primary flow

A technology for safety devices and nuclear reactors, which is applied to nuclear reactors, cooling devices, nuclear reactor monitoring, etc., and can solve problems such as poor stability, adverse effects of various functions and/or mechanical strength, and insufficient cooling of absorbing needles with coolant.

Active Publication Date: 2017-08-18
COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0014] Practice has proved that in the above technical solution, the absorption needle cannot be cooled sufficiently by the coolant flowing through the assembly
As mentioned earlier, insufficient cooling of the absorption needles may adversely affect the various functions and / or mechanical strength of their components
[0015] In addition, it has been proved that the stability of the above technical solutions is relatively poor

Method used

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  • Passive activation safety device for nuclear reactor on abnormal dropping in primary flow
  • Passive activation safety device for nuclear reactor on abnormal dropping in primary flow
  • Passive activation safety device for nuclear reactor on abnormal dropping in primary flow

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Embodiment Construction

[0148]In a nuclear reactor, heat from the fission zone is transferred to at least one coolant. Typically, a device includes several components. Some assemblies contain fissionable material, and others contain control rods, which control neutron activity. The remaining components are used to form passive trigger-type safety devices to stop or slow down neutron activity if the reactor malfunctions.

[0149] will now refer to figure 1 Through 6, the passive trigger type safety device provided by the embodiment of the present invention is described in detail.

[0150] The device essentially comprises a protective sleeve 200 for insertion into the core of the reactor. A part of said protective jacket 200 serves as a core zone 240 , which is oriented in a transverse direction perpendicular to the longitudinal direction 3 of the fission zone 10 of the reactor. This core zone 240 is always located below the fission zone 10 because the protective jacket 200 is fixed during operatio...

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Abstract

The present invention relates to a manual actuation safety device for a nuclear reactor. The manual actuation safety device includes: a sleeve unit (200) which has a coolant passing there-through in a vertical direction (3) and is extended in the substantially vertical direction (3) in an operation; and a movable cartridge unit (100) which is movably installed in the sleeve unit (200) in the vertical direction (3). The movable cartridge unit (100) includes a first support unit (110) spaced apart from a neutron absorber in the vertical direction (3). The sleeve unit (200) includes a second support unit (210). The first and second support units (110,210) are arranged to face each other. When the flow amount of the coolant passing through the sleeve unit (200) in the vertical direction (3) (Qf) is higher an operation flow amount (Q), the coolant lifts the movable cartridge unit (100) in the sleeve unit (200) while applying a force sufficient for maintaining the lifting arrangement to the movable cartridge unit (100).

Description

technical field [0001] The invention relates to the technical field of nuclear reactors. More specifically, it relates to a passive trigger type safety device for interrupting neutron activity in a nuclear reactor when the flow rate of the primary circuit coolant (also known as heat carrier) of the reactor core is abnormally reduced. [0002] The invention is particularly applicable to but not limited to the field of fast neutron reactors, especially fast neutron reactors using liquid metal sodium as a primary loop coolant. Background technique [0003] In reactors whose core is cooled by coolant, such as liquid metal sodium cooled fast neutron reactors (RNR-Na), reactivity control is generally achieved through multiple safety devices that can stop neutron reactions. Redundancy and technical differentiation of multiple safety devices in the same reactor should minimize the possibility of failure of the above-mentioned stop function. [0004] The working principle of these ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C9/02
CPCG21C9/02G21C1/02G21C7/103G21C9/027G21D3/06Y02E30/30G21C9/00G21C15/28G21C17/025
Inventor 丹尼斯·洛伦佐伊莎贝尔·格纳特-狄来海泽维尔·詹宁格罗斯伯纳德·瓦伦丁吉勒斯·阿瓦基安
Owner COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES