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Reactor core of beryllium-water moderated high-flux engineering test reactor

A high-flux, test reactor technology, applied in moderator/core structure, nuclear engineering, reactor, etc., can solve neutron leakage and other problems

Inactive Publication Date: 2014-12-03
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, the upper and lower ends of the core cannot be surrounded by beryllium, resulting in neutron leakage

Method used

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  • Reactor core of beryllium-water moderated high-flux engineering test reactor
  • Reactor core of beryllium-water moderated high-flux engineering test reactor
  • Reactor core of beryllium-water moderated high-flux engineering test reactor

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Embodiment Construction

[0022] The present invention will be described in further detail below in conjunction with the accompanying drawings and embodiments.

[0023] Such as figure 2 , image 3 As shown, the beryllium water moderated high flux engineering test reactor core of the present invention is composed of a central fuel assembly, side reflectors, upper and lower reflectors, isotope targets 7 and control rods 9; wherein the central fuel assembly includes fuel assemblies 5 , fuel assembly E with target + beryllium rod in the center, fuel assembly F with beryllium rod in the center; the side reflection layer includes water grid element 1, beryllium assembly 2, isotope target 7; wherein water grid element 1, beryllium assembly 2, fuel Component 5 and control rod 9 are the same as the existing CETR.

[0024] The center of the fuel assembly F is a beryllium rod, and the upper and lower reflective layers of the fuel assembly F are composed of aluminum + water + beryllium from the outside to the i...

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Abstract

The invention belongs to the reactor design technical field, and particularly relates to a reactor core of a beryllium-water moderated high-flux engineering test reactor. The reactor core is composed of a central fuel assembly, side reflective layers, upper reflective layers, lower reflective layers, isotopic target members and control rods; each side reflective layer comprises water gate elements, beryllium assemblies and the isotopic target members; the central fuel assembly comprises fuel assemblies; the central fuel assembly also comprises fuel assemblies each having the center with a target and a beryllium rod, and fuel assemblies each having the center with a beryllium rod; the center of each of the fuel assemblies is the beryllium rod, the upper reflective layer and the lower reflective layer of each of the fuel assemblies are each composed of aluminum, water and beryllium from outside to inside, namely the upper end part and the lower end part are each filled with a target member (C); the center of each of the fuel assemblies is composed of the beryllium rod and the external target member, the upper reflective layer and the lower reflective layer of each of the fuel assemblies are each composed of aluminum, water, target and beryllium from outside to inside, namely the upper end part and the lower end part are each filled with a target member (D). The reactor core has the isotope yield increased by 49% compared with a CETR adopted reactor core.

Description

technical field [0001] The invention belongs to the technical field of reactor design, in particular to a beryllium water moderated high flux engineering test reactor core. Background technique [0002] The initial design of China Engineering Test Reactor (CETR) mainly refers to the French JHR reactor. [0003] There are only 37 cells in the pressure shell of the French JHR reactor, referred to as the small pressure shell scheme: 37 cells are inserted into 34 fuel assemblies, and 3 cells can be placed in material channels, and other material targets can be placed in the center of fuel assemblies The core layout is not flexible enough; the reactor is mainly responsible for material testing, and there is no central heat sink, so the thermal neutron fluence rate is low, and isotope production is not considered; 27 sets of control rods are arranged in the center hole of the fuel assembly, and the replacement is inflexible . [0004] The CETR design also adopted the small press...

Claims

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Application Information

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IPC IPC(8): G21C3/04G21C5/16
CPCY02E30/30
Inventor 吴英华
Owner NUCLEAR POWER INSTITUTE OF CHINA