Design transient determination method for sodium-cooled fast reactor nuclear power station cooling agent system and member

A coolant system, sodium-cooled fast reactor technology, applied in nuclear power generation, cooling devices, reactors, etc., can solve problems such as unsuitability of sodium-cooled fast reactors

Active Publication Date: 2009-09-30
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, due to the differences in reactor principles and coolants, the design transient determinati

Method used

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  • Design transient determination method for sodium-cooled fast reactor nuclear power station cooling agent system and member
  • Design transient determination method for sodium-cooled fast reactor nuclear power station cooling agent system and member

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Embodiment Construction

[0012] The technical solution of the present invention will be further elaborated below through specific examples.

[0013] The thermal power is 65MWt, and the test power is 20Mwe. The pool-type sodium-cooled fast reactor, through three steps to determine its design transient method and obtain the generally available design transient conditions. Specific steps are as follows:

[0014] Step 1. Identify the design codes used for the coolant system and components

[0015] Design transients are strongly dependent on the design codes adopted for the coolant system and components of the analyzed plant. The world's most common codes for sodium-cooled fast reactors are the American Mechanical Engineering Boiler and Pressure Vessel Code (ASME for short) and the French RCC-M code.

[0016] Taking the ASME code as an example, it divides several limit allowable criteria for the failure modes of mechanical equipment and systems, and determines whether the design meets the specifications ...

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Abstract

The invention belongs to fast fission reactor technology field and discloses a design transient determination method for sodium-cooled fast reactor nuclear power station cooling agent system and member. The method comprises three steps: defining design standard of cooling agent system and member, determining classification rule of design transient, determining design transient status and circulation times. The invention adopts American mechanical engineering boiler and pressure container standard (simply ASME) and France RCC-M standard. The design transient status of sodium-cooled fast reactor is classified to five conditions: normal operation condition, middle frequency accident condition, sparse accident condition, limit accident condition, experiment condition. The circulation times of a condition in service life of a reactor is target value of transient impact to be experienced by cooling agent system and member in service life of a reactor. The method satisfies design demand for sodium-cooled fast reactor.

Description

technical field [0001] The invention belongs to the technical field of fast fission reactors, and in particular relates to a design transient determination method for a coolant system and components of a sodium-cooled fast reactor nuclear power plant. Background technique [0002] Design is the leader of all work in nuclear power plant construction, and in power plant design work, overall design is the core content of design work. Design transient refers to various transient conditions experienced by nuclear power plant coolant systems and components during the design life. Design transient conditions are the classification of design transients according to certain rules, which are often related to the mechanical evaluation specifications of coolant systems and components. , to determine the design transient conditions is the main work of the overall design of the reactor. [0003] The overall design ideas and schemes vary with the reactor type of the designed nuclear power...

Claims

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Application Information

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IPC IPC(8): G21C15/00
CPCY02E30/34Y02E30/30
Inventor 杨红义
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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