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Nuclear reactor core capable of improving neutron flux rate

A neutron fluence rate, nuclear reactor technology, applied in the direction of reactor, moderator/core structure, nuclear engineering, etc., can solve problems such as insufficient, thermal neutron fluence rate increase, etc., to achieve fission neutron fluence rate The effect of high, fast neutron fluence rates

Active Publication Date: 2013-03-20
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Generally, the antineutron trap core is used to increase the thermal neutron fluence rate of the reflective layer, but the thermal neutron fluence rate is not increased enough

Method used

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  • Nuclear reactor core capable of improving neutron flux rate
  • Nuclear reactor core capable of improving neutron flux rate
  • Nuclear reactor core capable of improving neutron flux rate

Examples

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Effect test

Embodiment 1

[0029] In this embodiment, the High Flux Engineering Test Reactor (HFETR) is taken as an example, the core is hexagonal, the reactor power is 90MW, 36 boxes of fuel assemblies, and thermal neutron moderation scheme. The core layout is as figure 1 .

[0030] The core is arranged in a hexagonal ring from the center to the outside, with a total of seven circles.

[0031] The beryllium thermal neutron trap area is followed by 1 box of beryllium blocks 1 in the center, 6 boxes of beryllium blocks 1 arranged in a quincunx shape on the periphery (first circle), 6 boxes of beryllium blocks 1 arranged in a quincunx shape in the second circle, and 6 boxes of control rods Body 3 composition. Among them, six boxes of control rod followers 3 are arranged on six corners.

[0032] The fuel assembly area is arranged in two outer circles (3rd and 4th circles) of the beryllium thermal neutron trap, consisting of 36 boxes of fuel assemblies 2 in total. Among them, six boxes of beryllium bloc...

Embodiment 2

[0043] This example takes the High Flux Engineering Test Reactor (HFETR) as an example. The core is hexagonal and the reactor power is 110MW. For the purpose of fast neutron breeding, fuel assemblies with high uranium content (core thickness 0.7mm, cladding thickness 0.4mm) are placed in 7 boxes in the center of 19 boxes of beryllium to form a fast neutron breeding area, pressurization or increase the flow rate method for deriving the heat of fission. Core layout as attached figure 2 shown.

[0044] The core is arranged in a hexagonal ring from the center to the outside, with a total of 7 circles.

[0045] The beryllium thermal neutron trap area consists of a center box of high-uranium fuel assemblies with fast neutron test channels 6, 6 boxes of high-uranium fuel assemblies arranged in a quincunx shape on the periphery (the first circle) 5, and a quincunx-shaped 1-2 circle. 1-1 (1 box of beryllium block-1 box of control rod follower-1 box of beryllium block) consists of 6...

Embodiment 3

[0055] In this embodiment, the High Flux Engineering Test Reactor (HFETR) is taken as an example, the reactor power is 135MW, and the core is loaded with 54 fuel assemblies, which are divided into three sub-cores, and each sub-core contains 18 fuel assemblies. The core layout is as image 3 .

[0056] The entire core is arranged in a hexagonal ring from the center to the outside, with a total of 9 circles, which is called the large core. The three sub-cores inside the large core are distributed in a 120° rotational symmetry in the core. The center of the sub-core is in the fourth circle of the large core, and the center of each sub-core is arranged outwardly in a hexagonal ring, with a total of 4 circles.

[0057] Each sub-core is arranged as follows:

[0058] The beryllium thermal neutron trap area is composed of 1 box of beryllium block 1 in the center, 18 boxes of beryllium block 1 and 1 box of control rod beryllium follower 3 arranged in a quincunx shape on the peripher...

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Abstract

The invention discloses a nuclear reactor core capable of improving neutron flux rate; the core is a circular structure; the center of the core is a Be thermal neutron well region, the circumference of which is a fuel component region, the circumference of which is a Be reflecting layer; the whole core is a circular structure. The maximum thermal neutron flux rate of the central Be thermal neutron well region can be over twice larger than that of the fuel region ; as the thermal neutron well region can be provided with fuel component with high uranium content, the fuel component center can form fast neutron region, therefore, the generated fission neutron has high flux rate.

Description

technical field [0001] The invention relates to a nuclear reactor core, in particular to the core of a multi-purpose research reactor requiring a high neutron fluence rate and a tool reactor mainly testing fuel materials. Background technique [0002] The current advanced research reactor design is a compact core with inverted (anti) neutron traps. At an appropriate power level, the core should be compressed as much as possible to increase the power density of the core to obtain a high fission neutron fluence rate. The highly undermoderated core is surrounded by a large volume of heavy water or beryllium, and a large number of fission neutrons leak from the core surface into the reflective layer to be moderated, forming a thermal neutron fluence rate peak. At the same power level, the smaller the volume of the power zone, the higher the thermal neutron fluence rate formed by leaked fission neutrons in the reflective layer. [0003] The ETR reactor in the United States has ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C5/14G21C5/18
CPCY02E30/40Y02E30/30
Inventor 吴英华
Owner NUCLEAR POWER INSTITUTE OF CHINA
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