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Reactor designing method

A design method and reactor technology, applied in computing, special data processing applications, instruments, etc., can solve the problems of βeff and Λ that are difficult to achieve calculation errors, and achieve good achievability, small calculation errors, and good stability.

Inactive Publication Date: 2013-04-17
NORTHWEST INST OF NUCLEAR TECH
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  • Summary
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  • Claims
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AI Technical Summary

Problems solved by technology

[0005] The object of the present invention is to provide a kind of calculation β that realizes conveniently, the result is reliable eff The Monte Carlo method of Λ and Λ is used in reactor design, which solves the problem of calculating β by the Monte Carlo method at present eff and Λ are difficult to realize or have large calculation errors

Method used

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Embodiment

[0171] Taking Xi'an Pulsed Reactor as an example, the application of the present invention is introduced.

[0172] In the first step, the detectors are used to measure the half-life and neutron spectrum of each delayed neutron precursor nucleus, and then the yields of six groups of delayed neutrons and the decay constants of the corresponding delayed neutron precursor nuclei are obtained by fitting, and the Parameters such as delayed neutron yield, neutron spectrum, and decay constant are written into the database in a certain format.

[0173] In the second step, the effective multiplication factor k(0) of the reactor is calculated using the unmodified original database. fissile nuclides in the database 235 U 238 The delayed neutron yield of U is increased and decreased by 0.25 times, and the corresponding database is called by Monte Cal program to calculate the effective multiplication factors k(0.25) and k(-0.25) of the reactor, and then use the formula k′(0)=2( k(0.25)-k...

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Abstract

The invention relates to a reactor designing method. The reactor designing method includes firstly detecting delayed neutron yield, writing the delayed neutron yield in a data base, then calculating effective share of delayed neutrons and neutron generation time, and then calculating dynamic characteristics of a reactor until design standards are met. The reactor designing method is not limited by reactor types and reactor core materials and can be widely applied to various types of reactors, Monte Carlo source programs are not required to be modified, and the reactor designing method has good realizability.

Description

technical field [0001] The invention belongs to a method for designing a reactor, and in particular relates to the calculation of two important dynamic parameters of the reactor—the effective share of delayed neutrons (β eff ) and neutron generation time (Λ), and apply them to the reactor design method. Background technique [0002] Effective fraction of delayed neutrons (β eff ) and neutron generation time (Λ) are two dynamic parameters necessary for the reactor design task, and they are very important for the analysis of the transient characteristics of the reactor. In recent years, β eff The calculation of Λ and Λ more and more adopts the Monte Carlo (Monte Carlo) method, because the Monte Carlo method has advantages that traditional calculation methods such as intuitive physical images and can describe arbitrary geometry do not have. However, Monte Carlo methods for continuous point sections cannot directly solve β eff and the flux adjoint function in the definition ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/50
Inventor 张良赵柱民陈伟江新标陈立新张信一郭和伟朱养妮
Owner NORTHWEST INST OF NUCLEAR TECH
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