Irradiation target for producing molybdenum-99 isotope in heavy water reactor

An isotope, heavy water reactor technology, applied in the field of irradiation targets, can solve the problems of low content and low efficiency, and achieve the effects of good quality, high efficiency and high specific activity

Pending Publication Date: 2021-06-15
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

But conventional fuel bundles use natural uranium, in which 235 The U content is too low to...

Method used

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  • Irradiation target for producing molybdenum-99 isotope in heavy water reactor
  • Irradiation target for producing molybdenum-99 isotope in heavy water reactor
  • Irradiation target for producing molybdenum-99 isotope in heavy water reactor

Examples

Experimental program
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Embodiment 1

[0040] see Figure 4 , the uranium-containing core 1-1 in this example uses 235 Some UO with U enrichment degree of 19.5wt% 2 The enriched uranium pellets are stacked sequentially along the axial direction of the cladding 1-2 to form the enriched uranium core, and the cladding 1-2 adopts a Zr-4 thick-walled tube with a wall thickness of 5.55mm. The enriched uranium pellet 1-14 has a diameter of 2 mm, and is tightly embedded in the cladding 1-2.

[0041] UO 2 Enriched uranium pellets 1-14 can be produced under neutron irradiation 99 Mo, while providing a suitable calorific value. The 18 fuel elements 1 in the outermost circle of the irradiation target are used Figure 4 As shown in the fuel element 1, there are 19 fuel elements 1 in the inner three circles. figure 2 Conventional fuel elements shown in , produced from a single irradiated target 99 The Mo isotope is at 1000 Curies, which is above the 6-day mark.

[0042] Of course, the enriched uranium pellets in this ex...

Embodiment 2

[0044] see Figure 5 , the uranium-containing core 1-1 in this example adopts the 235 Several UO with a U enrichment degree of 15.0wt% and a diameter of 2.7mm 2 The enriched uranium pellets are packed into the middle thick-walled tube 4 of Zr-4 material with a through hole on the central axis, and then the middle thick-walled tube 4 is packed into the cladding 1-2 made of thin-walled Zr-4 material with a thickness of 0.4mm. Enriched uranium core formed inside. Wherein, the outer diameter of the middle thick-walled tube 4 is 12.2 mm, and the inner diameter is 4.75 mm.

[0045] UO 2 of enriched uranium pellets can be produced under neutron irradiation 99 Mo, while providing a suitable calorific value. The 18 elements in the outermost circle of the irradiation target adopt Figure 5 The fuel element 1 shown in , the inner three circles of 19 fuel elements 1 adopt figure 2 Conventional fuel elements shown in , produced from a single irradiated target 99 The Mo isotope is ...

Embodiment 3

[0048] see Figure 6 , in this example the enriched uranium core adopts the 235 UO with 10.0wt% U enrichment 2 The enriched uranium coating 1-11 with a thickness of 160 μm is coated on the outer surface of the support tube 1-12 with an outer diameter of 11.8 mm and an inner diameter of 9.8 mm. In this example, the support tube 1-12 is made of stainless steel.

[0049] Then add a cladding 1-2 made of Zr-4 with an inner diameter of 12.3mm outside the enriched uranium core to form a "sandwich" structure.

[0050] UO 2 Enriched uranium coatings 1-11 can be produced under neutron irradiation 99 Mo, while providing a suitable calorific value. The 18 fuel elements in the outermost circle of the irradiation target adopt Figure 6 The fuel element 1 shown in , the inner three circles of 19 fuel elements 1 adopt figure 2 Conventional fuel elements shown in , produced from a single irradiated target 99 The Mo isotope is above 1000 Curies.

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Abstract

The invention relates to the technical field of fission type nuclear reactors, and especially relates to an irradiation target for producing a molybdenum-99 isotope in a heavy water reactor. The irradiation target comprises a fuel rod bundle; the fuel rod bundle comprises a plurality of fuel elements and end plates welded to the two ends of the fuel elements; and each fuel element comprises a cladding, a uranium-containing core arranged in the cladding and end plugs welded to the two ends of the cladding, the uranium-containing core in at least one fuel element is a rich uranium core provided with rich uranium fuel, and the <235>U enrichment degree of the rich uranium fuel ranges from 6.0 wt% to 20.0 wt%. Compared with the prior art, the method disclosed by the invention has the advantages that the characteristic that the heavy water reactor is refueled without stopping the reactor is fully utilized, the <99>Mo with short half-life period can be continuously produced by utilizing the existing reactor, a new irradiation facility does not need to be specially constructed, and the <99>Mo produced by using the enriched uranium is high in efficiency and good in quality, namely high in specific activity; and when the irradiation target is used for producing <99> Mo, the influence on power generation of a nuclear power plant can be reduced to the maximum extent.

Description

technical field [0001] The invention relates to the technical field of fission nuclear reactors, in particular to an irradiation target for producing molybdenum-99 isotope in a heavy water reactor. Background technique [0002] Nuclear medicine is an indispensable and important subject in medicine. It plays a special role in the diagnosis and treatment of human diseases and has developed rapidly in recent years. 99m Tc can be combined with a variety of ligands to form a variety of organ and functional imaging agents, which can be used to diagnose various diseases and judge changes in the function of human organs. According to data from Nature News & Comment, the world uses 99m The clinical diagnosis of Tc-related imaging technology reaches 30 million to 40 million person-times, accounting for 80% of all nuclear medicine applications. [0003] 99m Tc has a very short half-life of only 6.02 hours and usually needs to be replaced by its parent isotope with a half-life of 66 ...

Claims

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Application Information

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IPC IPC(8): G21G1/02G21G1/00G21K5/08
CPCG21G1/001G21G1/02G21K5/08G21G2001/0036Y02E30/30
Inventor 陈芙梁卢俊强周云清韩宇叶青朱丽兵
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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