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Pressurizer heater for the primary cooling system of a pressurized-water nuclear reactor

A nuclear reactor, heating rod technology, applied in nuclear reactors, thermal reactors, non-uniform reactors, etc., can solve problems such as leakage, shell rupture, damage to heating rod heating components, etc.

Active Publication Date: 2008-12-31
FRAMATOME ANP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

In fact, the outer shell of one of these heating rods sometimes cracks so that the inside of the heating rod communicates with the water in the regulator
[0005] [05] The result of this leak is damage to the heating element of the heating rod, causing the heating rod to stop working, and even causing pressurized water to leak out of the regulator through the internal gap of the heating rod

Method used

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  • Pressurizer heater for the primary cooling system of a pressurized-water nuclear reactor
  • Pressurizer heater for the primary cooling system of a pressurized-water nuclear reactor
  • Pressurizer heater for the primary cooling system of a pressurized-water nuclear reactor

Examples

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Embodiment Construction

[0031] [31] Figure 1 shows the main circuit 1 of a pressurized water nuclear reactor. The circuit 1 has a tank 2 in which a nuclear fuel assembly, a steam generator 4 equipped with a primary part (parties primaire) and a secondary part (partie secondaire), a primary pump 6 and a stabilizer 8 are arranged. The box 2, the steam generator 4 and the pump 6 are connected by a main-stage pipe section 10. Circuit 1 is equipped with main-stage water, which is pumped by pump 6 toward tank 2, passes through tank 2, undergoes heating, contacts the fuel assembly, and then passes through steam generator 4 before returning to the suction of pump 6 The main part of the. The primary water heated in the tank 2 releases its heat to the secondary water in the steam generator 4 through the secondary part of the generator. The secondary water circulates in a non-illustrated secondary circuit in a closed loop. It evaporates as it passes through the generator 4, and the steam thus produced drives a stea...

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Abstract

The invention relates to a heating rod for a pressurizer of a primary cooling system of a pressurized-water nuclear reactor, the rod comprising a metal outer shell (36) of longitudinally elongate shape having an external surface (62), and a heating element (40) mounted inside the shell (36). It comprises an anti-corrosion coating (60) covering at least part of the external surface (62) of the shell (36).

Description

Technical field [0001] [01] The present invention generally relates to the heating rods of the main loop regulator of a pressurized water nuclear reactor. [0002] [02] More precisely, according to the first embodiment, the present invention relates to a heating rod of a main loop regulator of a pressurized water nuclear reactor. The heating rod has a metal shell and a heating component, and the metal shell has a longitudinally extending shape, The metal shell has an outer surface, and the heating component is installed in the shell. [0003] [03] This kind of heating rod is usually installed in the lower part of the stabilizer and immersed in the water of the main circuit, which partially fills the stabilizer. These heating rods are used when the working pressure of the main loop of the reactor is to be increased. They heat water to its boiling temperature, causing a portion of it to volatilize. Background technique [0004] [04] Facts have proved that leakage occurs on the heat...

Claims

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Application Information

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IPC IPC(8): H05B3/82G21C1/09
CPCC25D3/12C25D5/36C25D7/04G21C1/09H05B3/82Y02E30/30
Inventor F·斯泰特兹朗M·富科Y·梅扎尔德P·斯科特
Owner FRAMATOME ANP