First criticality method for anti-neutron trap research reactor

A subcritical and antineutron technology, applied in the field of atomic energy, can solve the problems that the water level method is difficult to implement, cannot meet the requirements of the first critical experiment, and cannot meet the requirements of the first criticality of this type of reactor.

Active Publication Date: 2019-05-10
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

The antineutron trap type research reactor has a compact core structure and many external channels, and most of them adopt the design of separating the core coolant circuit from the external moderator circuit, which makes it difficult to implement the traditional water level method and cannot meet the requirements of this type of reactor. first critical requirement
In addition, due to the small loading of fuel assemblies in the core, in order to ensure that the reactor has sufficient backup r

Method used

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  • First criticality method for anti-neutron trap research reactor
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Embodiment Construction

[0022] The technical solutions of the present invention will be further specifically described below through the embodiments and in conjunction with the accompanying drawings. In the specification, the same or similar reference numerals indicate the same or similar contents. The following description of the embodiments of the present invention with reference to the accompanying drawings is intended to explain the general inventive concept of the present invention, but should not be construed as a limitation of the present invention.

[0023] According to the basic idea of ​​the present invention, the safety and effect of the first criticality are improved by combining the component method and the rod position method.

[0024] refer to figure 1 and figure 2 As shown, the antineutron trap type research reactor first critical method of the embodiment of the present invention comprises:

[0025] S1: subcritical extrapolation using the component method;

[0026] S2: When the d...

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Abstract

The invention provides a first criticality method for an anti-neutron trap research reactor. The first criticality method comprises the following steps: performing the subcritical extrapolation by adopting an element method; when the difference between an extrapolated result and an actual fuel assembly loading number of a core is less than 1, switching the element method critical extrapolation torod position method critical extrapolation, under the current core loading, inserting all control rods into the core, then loading a fuel assembly into the core, gradually lifting the control rods step by step, and carrying out the subcritical extrapolation by adopting the rod position of the control rods, gradually transiting the reactor to the critical state step by step, thereby realizing the first criticality. By combining the element method and the rod position method, the problem that a single criticality experiment method does not meet the requirements of the first criticality experiment of the anti-neutron trap research reactor can be solved.

Description

technical field [0001] The invention relates to the field of atomic energy, and further relates to a method for the first criticality of an antineutron trap type research reactor. Background technique [0002] The first criticality is a key link in the construction process of a research reactor and the only way to pass, marking that the reactor has the conditions to increase its power and gradually transfer to operational applications. The critical methods commonly used in reactors include water level method, component method and control rod rod level method, which method depends on the actual situation of the reactor and its own characteristics. The water level method refers to gradually adding heavy water or light water to the core to reduce the leakage of neutrons under a certain fuel load, so that the reactor is gradually approaching the critical state. The element method makes the reactor gradually approach and finally reach the critical state by adding fuel elements t...

Claims

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Application Information

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IPC IPC(8): G21C1/30
CPCY02E30/30
Inventor 袁履正王玉林金华晋柯国土吕征刘兴民朱吉印肖诗刚王理玉郑伍钦
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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