Recovery method of unqualified powder from MOX preparation process

A technology of preparation process and recovery method, which is applied in the field of recovery of unqualified products in the process of nuclear fuel preparation, can solve the problems of single, powder accumulation and treatment methods, and achieve the effects of improving utilization rate, meeting control requirements, processing effect and reliability

Active Publication Date: 2018-01-19
THE 404 COMPANY LIMITED CHINA NAT NUCLEAR +1
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AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a method for recycling unqualified powder in the MOX preparation process, solve the problems of powder accumulation and single treatment method, and realize the effective recovery and utilization of unqualified powder

Method used

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Embodiment Construction

[0023] The present invention will be described in detail below in conjunction with specific embodiments.

[0024] The MOX preparation process unqualified powder recovery method of the present invention comprises the following steps:

[0025] Step 1: Calculate the required unqualified MOX powder with a filling rate of 15-35%, and feed cooling water at 10-40°C at a speed of 1-50L / min to avoid powder compaction, and use a speed of 1-5r / min Mix for 5-30 minutes.

[0026] Step 2: Sampling the mixed unqualified powder and analyzing the uranium and plutonium content, impurity content, particle size, specific surface area, bulk density, O / M and other items.

[0027] Step 3: For the unqualified powder with heavy metal impurities exceeding the standard, transfer to the water normal line for chemical dissolution recovery treatment;

[0028] Step 4: For powders with volatile impurity content or unqualified O / M, select the corresponding sintering boat according to the amount of material ...

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Abstract

The invention belongs to the field of recovery technology of unqualified products from nuclear fuel preparation process and specifically relates to a recovery method of unqualified powder from the MOXpreparation process. The method comprises the following steps: calculating required unqualified MOX powder, introducing cooling water and mixing; analyzing uranium plutonium content, impurity content, granularity, specific surface area, apparent density and O/M; carrying out chemical dissolution recovery treatment on unqualified powder with elevated level of heavy metal impurities; treating powder with volatile impurity content or unqualified O/M by selecting a corresponding sinter boat according to required treatment quantity and internal space of a calcining furnace and uniformly laying unqualified powder into the sinter boat, introducing Ar-H2 gas mixture into the calcining furnace, regulating H2 content according to O/M, slowly heating, carrying out thermal insulation, and cooling thecalcining furnace to room temperature after thermal insulation; and treating MOX powder with unqualified uranium plutonium content by adding UO2 or PuO2 powder according to the uranium plutonium content analysis result to regulate the uranium plutonium content of the powder. According to the invention, effective utilization of unqualified powder can be realized.

Description

technical field [0001] The invention belongs to the technical field of recycling unqualified products in the nuclear fuel preparation process, and in particular relates to a method for recycling unqualified powder in the MOX preparation process. Background technique [0002] During the preparation of MOX pellets, a variety of unqualified powders will be produced, the main components of which are uranium and plutonium oxides. Because uranium and plutonium metals are non-renewable limited precious resources and have strong radioactivity, and because the powder particle size is extremely small, they are easy to float in the small room with the air flow disturbance, which affects the operation and control of precision equipment. Therefore, it is necessary to recycle the unqualified powder to avoid material loss, radioactive pollution and damage to equipment. [0003] At present, the traditional fuel pellet recovery technology simply temporarily stores the powder in the collecti...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/42G21C19/46
CPCY02E30/30Y02W30/50
Inventor 艾利君郭亮王斌李琪
Owner THE 404 COMPANY LIMITED CHINA NAT NUCLEAR
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