Porous Adsorbent for Trapping Radioactive Iodine Gas and Method of Manufacturing The Same

Patent metadata

Field	Value
Publication number	US-2016361701-A1
Application number	US-201414580628-A
Country	US
Kind code	A1
Filing date	Dec 23, 2014
Priority date	Dec 24, 2013
Publication date	Dec 15, 2016
Grant date	—

Abstract

Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same.
An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use.
Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.
In addition, since an iodine gas is trapped using inexpensive bismuth, instead of expensive silver, in consideration of trapping a large amount of a radioactive iodine gas, the adsorbent has very excellent economic feasibility.

First claim

What is claimed is:

1 . A method of manufacturing a radioactive iodine gas adsorbent, comprising the following steps of:
(a) preparing a mixed solution by mixing a solution including 10 to 20 wt % of bismuth nitrate and a solution including 10 to 20 wt % of polyvinylalcohol; (b) preparing a mixture by drying the mixed solution to remove moisture; (c) preparing an oxide by heat-treating the mixture in an atmospheric ambience to remove the polyvinylalcohol; and (d) reducing the oxide to a bismuth element state by heat-treating the oxide in a hydrogen ambience.

2 . The method according to claim 1 , wherein, in the step (a), the solution including 10 to 20 wt % of bismuth nitrate includes 10 to 50 ml of nitric acid per 100 ml of distilled water.

3 . The method according to claim 1 , wherein the drying in the step (b) is performed at 40 to 70° C. for 1 to 4 days.

4 . The method according to claim 1 , wherein the thermal treatment in the step (c) is performed in an atmospheric ambience at 400 to 500° C. for 2 to 3 hours.

5 . The method according to claim 1 , wherein the reduction in the step (d) is performed in a 4% hydrogen ambience at 300 to 350° C. for 6 to 12 hours.

6 . A radioactive iodine gas adsorbent manufactured by the manufacturing method according to claim 1 .

7 . The adsorbent according to claim 6 , wherein the adsorbent is a porous.

8 . A method of trapping a radioactive iodine gas, comprising:
trapping a gas containing a radioactive iodine gas by passing through the adsorbent of claim 6 .

9 . The method according to claim 8 , which is performed at 200 to 250° C. for 24 hours.

Assignees

• Korea Atomic Energy Res

Inventors

• Yang Jae Hwan
• Shin Jin-Myeong
• Park Jang Jin
• Park Geun-Ii

Classifications

• B01D53/02

  by adsorption, e.g. preparative gas chromatography {(solid sorbent compositions B01J20/00, preparation of inorganic compounds or elements C01)} · CPC title

• B01D53/685

  by treating the gases with solids · CPC title

• G21F9/02

  Treating gases · CPC title

• B01J20/02 Primary

  comprising inorganic material · CPC title

• B01D2253/1122

  Metals · CPC title