The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
Dec. 19, 2017

Filed:

Dec. 26, 2014
Applicant:

Korea Atomic Energy Research Institute, Daejeon, KR;

Inventors:

Sang Ho Na, Daejeon, KR;

See-Hwan Park, Daejeon, KR;

Ho-Dong Kim, Daejeon, KR;

Dae-Yong Song, Daejeon, KR;

Hee-Sung Shin, Daejeon, KR;

Bo-Young Han, Seoul, KR;

Hee Seo, Gyeonggi-do, KR;

Byung-Hee Won, Daejeon, KR;

Attorney:
Primary Examiner:
Int. Cl.
CPC ...
G21C 3/62 (2006.01); G21C 21/04 (2006.01); G21C 3/02 (2006.01); G21C 3/04 (2006.01);
U.S. Cl.
CPC ...
G21C 3/623 (2013.01); G21C 3/02 (2013.01); G21C 21/04 (2013.01); G21C 2003/045 (2013.01); G21Y 2004/40 (2013.01); Y02E 30/38 (2013.01);
Abstract

Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.


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