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A substoichiometric uo 2-x Measuring method of uranium content in fuel

A sub-stoichiometric and measurement method technology, applied in the field of measurement of uranium content in sub-stoichiometric UO2-x fuel, can solve problems such as errors, and achieve the effects of less interference, fast measurement speed, and high data accuracy

Active Publication Date: 2020-10-09
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] Metal uranium is a very active metal, which cannot be measured by ordinary chemical analysis methods, so it is generally measured by UO 2-x Fuel O / U ratio to estimate UO 2-x The content of uranium metal in the fuel, but this method has a large error

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0027] Example 1: Substoichiometric UO 2-x Measurement of Uranium Content in Fuel (1)

[0028] The method for measuring substoichiometric UO is as follows 2-x The uranium content in the standard fuel is known to be 0.5 wt%.

[0029] (1)UO 2-x Pellet Crushing

[0030] In the Ar gas protection glove box, UO with a mass of 4g 2-x The pellets were broken, passed through a 80-mesh sieve, and then put into a vacuum drying oven for drying treatment for 1 hour to obtain UO 2-x powder.

[0031] (2)UO 2-x Powder first dehydrogenation treatment

[0032] The broken UO 2-x Powder placed in 2×10 -2 Under the vacuum condition of Pa, heat preservation treatment at 600°C for 2 hours to obtain UO after dehydrogenation 2-x powder.

[0033] (3)UO 2-x Hydrogenation of metal uranium in powder

[0034] UO after dehydrogenation 2-x powder in pure H 2 Under ambient conditions, treat at 500°C for 1 hour to obtain hydrogenated UO 2-x powder.

[0035] (4) UO after hydrogenation 2-x Powd...

Embodiment 2

[0037] Example 2: Substoichiometric UO 2-x Measurement of Uranium Content in Fuel (2)

[0038] The method for measuring substoichiometric UO is as follows 2-x The uranium content in the standard fuel is known to be 0.75 wt%.

[0039] (1)UO 2-x Pellet Crushing

[0040] In the Ar gas protection glove box, the UO with a mass of 4.5g 2-x The pellets were broken, passed through a 90-mesh sieve, and then placed in a vacuum drying oven for 1.5 hours to obtain UO 2-x powder.

[0041] (2)UO 2-x Powder first dehydrogenation treatment

[0042] The broken UO 2-x Powder placed in 3×10 -2 Under the vacuum condition of Pa, heat preservation treatment at 700°C for 3 hours to obtain UO after dehydrogenation 2-x powder.

[0043] (3)UO 2-x Hydrogenation of metal uranium in powder

[0044] UO after dehydrogenation 2-x powder in pure H 2 At 550°C for 1.5 hours under ambient conditions, the hydrogenated UO 2-x powder.

[0045] (4) UO after hydrogenation 2-xPowder secondary dehydro...

Embodiment 3

[0047] Example 3: Substoichiometric UO 2-x Measurement of Uranium Content in Fuel (Ⅲ)

[0048] The method for measuring substoichiometric UO is as follows 2-x The uranium content in the standard fuel is known to be 1 wt%.

[0049] (1)UO 2-x Pellet Crushing

[0050] In the Ar gas protection glove box, UO with a mass of 5g 2-x The pellets were broken, passed through a 100-mesh sieve, and then dried in a vacuum drying oven for 2 hours to obtain UO 2-x powder.

[0051] (2)UO 2-x Powder first dehydrogenation treatment

[0052] The broken UO 2-x Powder placed in 4×10 -2 Under the vacuum condition of Pa, heat preservation treatment at 800°C for 4 hours, the dehydrogenated UO 2-x powder.

[0053] (3)UO 2-x Hydrogenation of metal uranium in powder

[0054] UO after dehydrogenation 2-x powder in pure H 2 Under ambient conditions, treat at 600°C for 2 hours to obtain hydrogenated UO 2-x powder.

[0055] (4) UO after hydrogenation 2-x Powder secondary dehydrogenation tre...

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PUM

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Abstract

The invention belongs to the technical field of nuclear fuel analysis and relates to a method for measuring the uranium content in substoichiometric UO<2-x> fuel. The method includes (1) subjecting the substoichiometric UO<2-x> fuel to crushing, sieving and drying treatment; (2) subjecting the substoichiometric UO<2-x> fuel after crushing, sieving and drying treatment to a first time of dehydrogenation; (3) hydrogenating metal uranium in the substoichiometric UO<2-x> fuel after the first time of dehydrogenation; and (4) subjecting the hydrogenated substoichiometric UO<2-x> fuel to a second time of dehydrogenation, collecting generated gas and calculating the uranium content through measuring the content of hydrogen in the gas. Through the method, the uranium content of the UO<2-x> fuel can be accurately measured so that the using performance of the UO<2-x> fuel can be further analyzed and evaluated better.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel analysis and relates to a substoichiometric UO 2-x Method for the measurement of uranium content in fuel. Background technique [0002] Substoichiometric UO 2-x Fuel is a special kind of nuclear reactor fuel whose main feature is that the O / U ratio is less than 2.0. with ordinary UO 2 Fuel compared to UO 2-x The fuel has the advantages of low fuel evaporation rate, good compatibility with Mo cladding, and good radiation stability, which makes it the preferred fuel for space nuclear power reactors. [0003] Substoichiometric UO 2-x Fuel is obtained by placing the UO 2 It is prepared by mixing, pressing and sintering with metal uranium (U) powder. UO 2-x Fuel at a temperature above 1100 ° C with UO 2-x Single phase exists; at temperatures below 1100°C UO 2-x The single-phase structure will decompose into metallic uranium (U) and UO 2 A mixture of two phases, when UO 2-x The properti...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N33/28
CPCG01N33/2835
Inventor 吴学志尹邦跃魏国良
Owner CHINA INSTITUTE OF ATOMIC ENERGY