Method for obtaining three-dimensional neutron flux density distribution in reactor core transient process of fast neutron reactor

A neutron flux density and fast neutron reactor technology is applied in the field of obtaining the three-dimensional neutron flux density distribution during the transient process of the fast neutron reactor core, and achieves the effects of strong adaptability, improved computing efficiency, and high computing accuracy

Active Publication Date: 2017-08-18
XI AN JIAOTONG UNIV
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Problems solved by technology

[0005] In order to overcome the difficulties of the above-mentioned physical phenomena and solve the problems in the prior art, the present invention provides a method for obtaining the three-dimensional neutron flux density distribution

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  • Method for obtaining three-dimensional neutron flux density distribution in reactor core transient process of fast neutron reactor
  • Method for obtaining three-dimensional neutron flux density distribution in reactor core transient process of fast neutron reactor
  • Method for obtaining three-dimensional neutron flux density distribution in reactor core transient process of fast neutron reactor

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Embodiment Construction

[0037] The invention decomposes the components of the neutron flux density with different time-varying rates and solves them separately on different time scales, thereby greatly reducing the amount of calculation. At the same time, the above process is applied to a more rigorous calculation of neutron transport, so as to ensure the calculation accuracy. The method flow is as follows figure 1 As shown, the invention includes the following aspects:

[0038] Step 1: Read the parameters required for the transient calculation of the fast neutron reactor, including reactor core geometry, core material layout, prefabricated homogenization cross-section parameters, prefabricated homogenization kinetic parameters, core inlet temperature and reactor Boundary conditions for core flow distribution. At the same time, pre-calculate the reactor core involved, including geometric modeling of regular triangular prisms or arbitrary triangular prisms, division of calculation areas, generation ...

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Abstract

The invention discloses a method for obtaining three-dimensional neutron flux density distribution in a reactor core transient process of a fast neutron reactor. A polygonal prism grid is adopted for the anisotropic neutron flux density of the reactor core of the fast neutron reactor to carry out fully-three-dimensional transportation space dispersion, a semi-spherical surface of a sixty-degree region is taken as a unit to carry out alternate scanning, and iterative format degradation in an angle parallel process is weakened; and the characteristics of the weak local effect and the global space coupling of the neutron flux density of the reactor core of the fast neutron reactor are considered, an estimated correction quasi-static strategy is adopted for neutron flux density change in a transient process to carry out time dispersion, ingredients of different change rates along with time in the neutron flux density can be decomposed, separated solution is carried out on different time scales, meanwhile, nonlinear iteration among above ingredients is avoided, and calculation efficiency is improved. The method for obtaining the three-dimensional neutron flux density distribution in the reactor core transient process of the fast neutron reactor has the advantages of being high in calculation accuracy and reasonable in calculated amount.

Description

technical field [0001] The invention relates to the technical field of fast neutron reactor core operation and safety, in particular to a method for obtaining the three-dimensional neutron flux density distribution in the transient process of the fast neutron reactor core. Background technique [0002] Fast neutron reactor is the main reactor type in the fourth-generation nuclear energy system. The average neutron energy of the core is more than one million times higher than that of the traditional thermal neutron fission-dominated pressurized water reactor. more neutrons. Excess neutrons can not only multiply nuclear fuel and improve the utilization rate of uranium resources; they can also be used to transmute highly radioactive and long-lived minor actinide nuclides (isotopes of neptunium, americium, curium, etc.) in nuclear waste, which can greatly shorten the time spent on nuclear waste. The required number of years for geological storage. Therefore, the development of...

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Application Information

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IPC IPC(8): G06F17/50G21C17/108
CPCG21C17/108G06F30/20Y02E30/30
Inventor 郑友琦何明涛曹良志吴宏春
Owner XI AN JIAOTONG UNIV
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