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Critical safety design method of fluidized bed in nuclear fuel post-treatment

A design method and criticality safety technology, applied in the field of criticality safety design of fluidized bed in nuclear fuel reprocessing, can solve problems not related to criticality safety design of fluidized bed, achieve multi-parameter optimal design and save design work Effect

Pending Publication Date: 2020-01-24
CHINA NUCLEAR POWER ENG CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] Regarding the design of the fluidized bed, there are some reports in the prior art. For example, Chinese patent application 201710950743.9 discloses a design method for fluidized bed drying and grading equipment, and Chinese patent application 201810770033.2 discloses a circulating fluidized bed recycling system based on CFD. Optimum design method for material pipe structure, Chinese patent application 201210115667.7 discloses a multi-furnace circulating fluidized bed boiler based on modular scale-up design, but none of them involve critical safety design of fluidized bed in nuclear fuel reprocessing

Method used

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  • Critical safety design method of fluidized bed in nuclear fuel post-treatment
  • Critical safety design method of fluidized bed in nuclear fuel post-treatment
  • Critical safety design method of fluidized bed in nuclear fuel post-treatment

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Embodiment Construction

[0031] The specific implementation manners of the present invention will be further described below in conjunction with the accompanying drawings.

[0032] Exemplary nuclear fuel reprocessing uses a fluidized bed configuration such as figure 1 As shown, it includes a heating section 1, a transition section 2 and an expanding section 3 connected in sequence from bottom to top.

[0033] The flow process of the criticality safety design method of the fluidized bed in the exemplary nuclear fuel reprocessing of the present invention is as follows figure 2 shown, including the following steps:

[0034] (1) Determine the preliminary design parameters: determine the parameters of uranium trioxide, such as uranium trioxide density, particle size range, etc., and conduct a preliminary design of the fluidized bed, mainly the dimensions and process parameters of the fluidized bed.

[0035] (2) Critical calculation of infinitely long cylinders: according to the determined uranium trioxi...

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Abstract

The invention belongs to the technical field of nuclear safety design, and relates to a critical safety design method of a fluidized bed in nuclear fuel post-treatment. The design method comprises thefollowing steps: (1) determining preliminary design parameters and carrying out preliminary design on the fluidized bed; (2) performing infinite length cylinder critical calculation; (3) drawing a volume ratio curve; (4) judging whether the volume ratio curve obtained in the step (3) is located below a limit value curve in the whole height or not; (5) modifying the equipment size and process parameters, and re-designing the fluidized bed in the step (1), drawing a volume ratio curve in the step (3) and judging in the step (4), or judging whether a design optimization space exists or not; and(6) carrying out critical recheck calculation on the design. By means of the design method, a large amount of design work can be saved under the condition that critical safety is met, and meanwhile equipment designers can adjust and optimize the design size and technological parameters within a certain range.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety design, and relates to a critical safety design method of a fluidized bed in nuclear fuel reprocessing. Background technique [0002] my country's nuclear industry is developing rapidly, and the number of spent fuel assemblies is also increasing, which puts forward higher requirements for my country's nuclear fuel reprocessing. The reprocessing of spent fuel is an important part of my country's closed nuclear fuel cycle. Its treatment process mainly includes the first stage of shear dissolution treatment, co-decontamination and separation treatment, plutonium line and uranium line treatment process. The uranyl nitrate solution after the pollution separation treatment is further purified, and then the feed liquid is evaporated and concentrated, and then converted into the final product of uranium trioxide. Due to the fissile nuclide processing involved, many process links of spent fuel repro...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G16C10/00
CPCG16C10/00Y02E30/30
Inventor 李云龙易璇邵增霍小东杨海峰于淼
Owner CHINA NUCLEAR POWER ENG CO LTD
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