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Experiment system for simulating water loss accident

An experimental system and a technology for water loss accident, applied in the field of reactors, can solve problems such as low experimental efficiency, and achieve the effect of improving experimental efficiency

Pending Publication Date: 2021-09-21
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In related technologies, the experimental efficiency of the experimental system is low

Method used

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  • Experiment system for simulating water loss accident
  • Experiment system for simulating water loss accident
  • Experiment system for simulating water loss accident

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Embodiment Construction

[0034] It should be noted that, in the case of no conflict, the embodiments in the application and the technical features in the embodiments can be combined with each other. Undue Limitation of This Application.

[0035] As part of the inventive concept of the present application, before describing the embodiments of the present application, it is necessary to analyze the reasons for the low experimental efficiency of the experimental system in related technologies, and obtain the technical solutions of the embodiments of the present application through reasonable analysis.

[0036] In related technologies, in order to test the bulge blasting performance of the cladding under LOCA accidents, it may be necessary to carry out multiple cladding bulge blast experiments. The cladding is subjected to bulge blasting to obtain the temperature distribution of the cladding, etc. The experimental system in the related art is not equipped with equipment for cooling the cladding. After th...

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Abstract

The embodiment of the invention provides an experiment system for simulating a water loss accident, which belongs to the technical field of reactors. The experiment system comprises test equipment and quenching equipment, the test equipment is provided with an experiment cavity for accommodating a cladding, and the test equipment is configured to perform bulging blasting on the cladding in the experiment cavity. The quenching equipment is configured to provide a fluid for quenching to the experiment cavity. And after the cladding is subjected to bulging blasting in the experiment cavity of the test equipment, fluid for quenching is provided for the experiment cavity through quenching equipment so as to quench the cladding subjected to bulging blasting. On one hand, the LOCA accident can be truly simulated by quenching the cladding subjected to bulging blasting through the quenching equipment, and on the other hand, the cladding can be rapidly cooled by quenching the cladding subjected to bulging blasting through the quenching equipment, so that an operator can conveniently take out the cladding and then replace another cladding to continue subsequent experiment operation, and thus the experiment efficiency is improved.

Description

technical field [0001] The present application relates to the technical field of reactors, in particular to an experimental system for simulating a loss of water accident. Background technique [0002] In the safety analysis of the nuclear reactor core, there is a hypothetical accident worthy of attention, that is, the Large Break Loss of Coolant Accident (LOCA for short). If a new fuel is to be used in a PWR, the performance of the fuel under LOCA must be studied to demonstrate its reliability under a possible LOCA accident and to provide test data for the core safety analysis program. [0003] During the LOCA process of PWR, the phenomenon of cladding bulging and blasting will inevitably occur. If the cladding is over-brittle, the cladding may break and block the entire flow channel; if the cladding is not over-brittle Shell, there may be extreme coplanar bulging and block part of the flow channel. [0004] During the operation of a nuclear power plant reactor, the perfo...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00C21D1/62C21D9/00
CPCG21C17/001C21D1/62C21D9/0068Y02E30/30
Inventor 武琦季松涛何晓军刁均辉李凯高永光关玺彤
Owner CHINA INSTITUTE OF ATOMIC ENERGY