Method of manufacturing uranium target to be soluble in basic solution and method of extracting radioactive mo-99 using the same

Patent metadata

Field	Value
Publication number	US-2020368820-A1
Application number	US-202016773779-A
Country	US
Kind code	A1
Filing date	Jan 27, 2020
Priority date	May 22, 2019
Publication date	Nov 26, 2020
Grant date	—

Abstract

Disclosed are a method of manufacturing a uranium target, the method including (a) a step of preparing a conjugate including a matrix and a uranium target green compact formed in the matrix; and (b) a step of performing thermo-mechanical treatment through additional heat treatment at 530° C. to 600° C. during a hot rolling pass in a process of hot-rolling the conjugate, and a method of extracting radioactive Mo-99 using the uranium target.

First claim

1 . A method of manufacturing a uranium target, the method comprising:
preparing a conjugate comprising a matrix and a uranium target green compact formed in the matrix; and performing a process of hot-rolling the conjugate comprising at least one additional-hot rolling pass comprising an additional-heat treatment at 530° C. to 600° C. and a rolling pass.

2 . The method according to claim 1 , wherein the uranium target is soluble in a basic solution.

3 . The method according to claim 1 , wherein a content of U-235 in the uranium target is 20% by weight or less.

4 . The method according to claim 1 , wherein the uranium target has a density of 3.0 gU/cm 3 to 10.0 gU/cm 3 .

5 . The method according to claim 1 , wherein, in the preparing, the uranium target green compact is manufactured by mixing and compacting a uranium-aluminum alloy powder and an aluminum powder, and a content of aluminum in the uranium-aluminum alloy powder is 20% by weight or less.

6 . The method according to claim 5 , wherein a content of the uranium-aluminum alloy powder in a total of the uranium-aluminum alloy powder and the aluminum powder is 10% by volume to 50% by volume.

7 . (canceled)

8 . The method according to claim 1 , wherein, in the performing, a surface temperature of a hot roll is 80° C. to 100° C.

9 . (canceled)

10 . (canceled)

11 . The method according to claim 1 , wherein the additional heat treatment in the performing is performed for a total of 5 hours to 20 hours.

12 . (canceled)

13 . The method according to claim 1 , wherein the additional-heat treatment in the performing is performed to change a U or UAl 2 phase in the conjugate to a UAl 3 or UAl 4 phase.

14 . A method of extracting radioactive Mo-99, the method comprising:
manufacturing a uranium target according to the method of claim 1 , and then dissolving the uranium target in a basic solution; and extracting radioactive Mo-99 from the basic solution containing the uranium target dissolved therein.

Assignees

• Korea Atomic Energy Res

Inventors

• Kim Ki Nam
• Park Sung Chan
• Jeong Yong Jin
• Lee Kyu Hong
• Kim Sung Hwan
• Cho Tae Won
• Park Jong Man

Classifications

• C22C1/047

  comprising intermetallic compounds {(C22C1/0441 takes precedence)} · CPC title

• G21G1/02 Primary

  in nuclear reactors (by thermonuclear reactions G21B; conversion of nuclear fuel G21C) · CPC title

• G21G4/08

  specially adapted for medical application (radiation therapy using radioactive sources A61N5/10) · CPC title

• C22C1/02

  by melting {(C22C1/1036 takes precedence)} · CPC title

• Y02P10/20

  Recycling · CPC title