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Boron carbide shielding assembly

A boron carbide and component technology, used in shielding, reactors, reducing greenhouse gases, etc., can solve problems such as complex structure and design life limit, and achieve the effect of increasing wear resistance, alleviating stress state, and solving pressure problems.

Active Publication Date: 2008-05-14
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a more practical boron carbide shielding assembly for the problem that the structure of the boron carbide shielding assembly in the prior art is complex and the design life is limited

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Embodiment Construction

[0013] The technical solution of the present invention will be further elaborated below in conjunction with the accompanying drawings.

[0014] The boron carbide shielding assembly described in this embodiment is arranged on the periphery of the reflector assembly of the sodium-cooled fast reactor, and is arranged in 4 layers, with a total of 230 boxes. Allow to cool. The basic design and operating parameters are shown in Table 1.

[0015] Table 1 Basic parameters of boron carbide shielding components

[0016] parameter name

value

shielding material

boron carbide

10 B enrichment (%)

19.8 (natural)

B in a box of components 4 C weight (kg)

2.4

Weight of a box of components (kg)

～32

Working life of components under rated power (effective days)

(1) The first floor

1440

(2) The second floor

1680

(3) The third floor

1920

(4) The fourth floor

224...

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Abstract

The invention discloses a component for shielding neutronic reactor core. The component consists of three parts: a head part, a middle part and a tail part; wherein, the head part is composed of a manipulation head and an upper transitional joint. The manipulation head is inosculated with component handling equipment and is also provided with an outlet hole for sodium; the external side of the upper transitional joint is provided with a locating block to guarantee the radial positioning among components, and the upper transitional joint is welded on the upper surface of a hex wrapper tube. The middle part is composed of a hex wrapper tube and a shield which is arranged in the wrapper tube. The tail part is composed of a lower transitional joint and a pin. The lower transitional joint is welded on the bottom surface of a hex wrapper tube and the pin is provided with an inlet hole for sodium. The invention uses high-density and hot-pressing a boron carbide pellet to guarantee that the boron carbide pellet dose not escape out of a rod after cracking, and at the same time an absorbing rod adopts a ventilation-typed top end plug to extract the helium gas produced in the B-10 (n, Alpha)reaction. The technical proposal of the invention is not only practical but also solves the bearing pressure of a casing on the absorbing rod effectively.

Description

technical field [0001] The invention belongs to the technical field of fast neutron reactors, in particular to fast neutron reactor core shielding components. Background technique [0002] The boron carbide shielding component is one of the core components of the sodium-cooled fast neutron reactor. It uses the 10B element in the natural boron carbide to absorb the neutrons that escape from the reflector component to protect the reactor internals and the reactor container from excessive neutralization. sub-irradiation and avoid secondary sodium activation in the intermediate heat exchanger. The boron carbide shielding assembly mainly consists of three parts, namely the head consisting of the operating head, the upper transition joint, etc., the middle part consisting of the hexagonal sleeve, the shielding rod placed in the sleeve, and the absorber rod bundle, and the lower transition The tail composed of connectors and pins. When working, the coolant sodium enters the compo...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C11/06
CPCY02E30/40Y02E30/30
Inventor 张汝贤
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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