Computing method of absolute neutron flux spectrum of refrigerant in reactor core active section

A calculation method and coolant technology, which are applied in the calculation field of reactor neutron flux spectrum, can solve problems such as insufficient meeting accuracy requirements, and achieve the effect of improving calculation accuracy

Active Publication Date: 2013-10-23
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

The commonly used core neutron transport calculation program can quickly give the absolute value of the neutron flux in the reactor under different core states. flux, and often only the ...

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  • Computing method of absolute neutron flux spectrum of refrigerant in reactor core active section
  • Computing method of absolute neutron flux spectrum of refrigerant in reactor core active section
  • Computing method of absolute neutron flux spectrum of refrigerant in reactor core active section

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Embodiment Construction

[0028] The present invention will be described in detail below with reference to the drawings and embodiments.

[0029] Take the absolute neutron flux spectrum of the coolant provided by the ACP1000 unit for the calculation of the source term as an example. There are 177 components in the core of this unit. First, the calculation of the core program is performed. From the calculation result of the core calculation program, the absolute value of the two groups of neutron flux in a certain equilibrium cycle life can be known. At this time, the boron concentration in the core Conditions such as the density and temperature of the coolant, the temperature of the fuel, and the nuclide density of the component under a certain burnup are also known. The Monte Carlo program is used to simulate the core for three-dimensional calculations. The calculation can be performed by simulating the entire core composed of 177 components, or a relatively simplified fuel assembly model can be used for...

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Abstract

The invention relates to a computing method of a neutron flux spectrum in a reactor, particularly to a computing method of an absolute neutron flux spectrum of a refrigerant in a reactor core active section. According to the computing method, a method combining reactor core neutron transport program with Monte Carlo program is used, the reactor core computing program is used for computing the absolute value of average flux of the reactor core, the flux ratio of the refrigerant and the reactor core, and the neutron flux distribution of a customized energy group in the refrigerant are generated through analog computation of the Monte Carlo program, and the absolute neutron flux spectrum distributed in different energy groups of the refrigerant in the reactor core active section is finally computed, so that the computing method of traditionally using the value of average neutron flux to compute related source items of the reactor is improved, and the computing accuracy is improved.

Description

Technical field [0001] The invention relates to a method for calculating the neutron flux spectrum of a reactor, in particular to a method for calculating the absolute neutron flux spectrum of a coolant in an active area of ​​a reactor core. Background technique [0002] A nuclear reactor is a device that emits energy through a neutron chain fission reaction. It is a relatively large and complex system. In order for the reactor to operate safely and economically, it is often necessary to know the distribution of neutron flux in the reactor. The distribution of neutron flux during operation of the reactor is affected by different factors in the reactor, so it is more complicated to calculate its time and space distribution. In order to adapt to different needs, the distribution of neutron flux in different regions of the reactor can be used It is obtained by different calculation methods, and the calculation accuracy and time consumption obtained by different methods are different...

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Application Information

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IPC IPC(8): G06F17/10
Inventor 霍小东易璇邵增杨海峰
Owner CHINA NUCLEAR POWER ENG CO LTD
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