Monte Carlo simulation method for active critical device in approximate critical process

A technology of critical devices and simulation methods, applied in special data processing applications, instruments, electrical digital data processing, etc., can solve the difficulties in calculating the infinite transport of external neutron sources, the difficulty of neutron detector range design flux value reference, It is impossible to obtain the neutron flux distribution of the detection point and other problems, and achieve the effect of correct and reliable calculation results of physical quantities
CN112069670APending Publication Date: 2020-12-11CHINA NUCLEAR POWER ENG CO LTD
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Patent Information

Authority / Receiving Office
CN · China
Current Assignee / Owner
CHINA NUCLEAR POWER ENG CO LTD
Publication Date
2020-12-11

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Abstract

The invention relates to a Monte Carlo simulation method for an active critical device in an approximate critical process, which is suitable for the field of neutronics physical analysis of a nuclearcritical device with an external neutron source. According to the invention, the method comprises the steps: decomposing a continuous neutron transport process into successive generations of analog calculation, and according to successive generations of system neutron effective proliferation factors and successive generations of physical quantity statistical counting, and carrying out the weightedsummation to obtain final calculation results of physical quantities such as nuclear critical device power level and neutron flux distribution are obtained. According to the method, Monte Carlo simulation of the transport process of the external neutron source in the approaching critical process of the nuclear critical device is achieved, and the situation that infinite transport calculation of the external neutron source of a certain generation is not terminated due to randomness of the Monte Carlo method is avoided; the Monte Carlo simulation method for the neutron transport process of theactive critical device is advanced and has engineering feasibility.
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Description

technical field

[0001] The invention relates to a neutronics physical analysis technology for a nuclear critical device, in particular to a Monte Carlo simulation method for an active critical device in the process of approaching criticality. Background technique

[0002] When carrying out nuclear criticality experiments, in order to better monitor the physical state of the nuclear criticality device, it is usually necessary to configure a certain intensity of external neutron sources in the nuclear criticality device, and at the same time arrange neutron detectors at different positions. The neutron flux distribution and its change rate are used to infer the characteristic parameters of the nuclear criticality device such as subcriticality and reactivity introduction rate, so as to carry out nuclear criticality-related experiments safely and efficiently.

[0003] For this reason, in the design of nuclear criticality devices, it is necessary to calculate and analyze the neut...

Claims

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