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Pressurized water reactor compact steam generator

A technology for steam generators and reactors, which is applied to the primary side of steam generators, reactors, nuclear reactors, etc., and can solve problems such as size reduction

Inactive Publication Date: 2015-01-28
WESTINGHOUSE ELECTRIC CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Thus, new steam generator designs are needed that reduce the size of the steam generator components that would benefit from being housed within the reactor vessel

Method used

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  • Pressurized water reactor compact steam generator
  • Pressurized water reactor compact steam generator
  • Pressurized water reactor compact steam generator

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Embodiment Construction

[0017] exist Figure 2-4 The embodiments of the hereafter claimed invention shown in describe a steam generator system for a pressurized water nuclear reactor employing a steam drum and recirculation loop piping external to the reactor containment vessel. The present invention changes the layout of the recirculation steam generator of a typical pressurized water nuclear reactor by relocating the functions of steam separation and feedwater preheating outside the containment vessel. Like reference numerals are used throughout the several drawings to designate corresponding parts. The steam generator system design and thermal-hydraulic conditions are selected to minimize the size of the steam generator component volume inside the containment. External vapor drum components can be isolated as needed during accident conditions and used as a secondary fluid inventory source for increased decay heat removal capability and tolerance to loss of feedwater events. The present invention...

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Abstract

A steam generator system for a pressurized water reactor which employs an external to containment steam drum and recirculation loop piping. The steam generator system changes the arrangement of a typical pressurized water reactor recirculation steam generator by relocating the functions of steam separation and feedwater preheating outside of the reactor coolant system. The steam generator system and thermal hydraulic conditions are selected in order to minimize the size of the steam generator heat exchanger component volume inside of the containment. The external steam drum component can be isolated in accident conditions when desired and is used as a source of secondary fluid inventory for improved decay heat removal capability and tolerance for loss of feedwater events. Thus, the steam generator component volume inside of the containment is reduced and the amount of maintenance required for the reactor coolant system components are similarly reduced.

Description

technical field [0001] The present invention relates generally to pressurized water nuclear reactors, and more particularly to steam generators for pressurized water reactors. Background technique [0002] In nuclear reactors used to generate electricity, such as pressurized water reactors, heat is generated by the fission of nuclear fuel, such as enriched uranium, and is transferred to coolant flowing through the reactor core. The core contains elongated nuclear fuel rods mounted close to each other in a fuel assembly structure through which coolant flows. The fuel rods are spaced from each other in a coextensive parallel array. Some of the neutrons and other atomic particles released during the nuclear decay of fuel atoms in a given fuel rod pass through the space between the fuel rods and impinge on fissionable material in adjacent fuel rods, thereby causing a nuclear reaction and heat generated by the core. [0003] Movable control rods are dispersed throughout the nu...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C1/32G21C15/12G21C15/16
CPCY02E30/32F22B37/327G21D1/006G21C1/322F22B1/023G21C15/16G21C15/12F22B37/22F22B37/261Y02E30/30Y02E30/00G21C1/32
Inventor M·C·埃文斯A·W·哈克尼斯C·泰勒W·E·卡明斯
Owner WESTINGHOUSE ELECTRIC CORP
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