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Development of metallic fuel materials -Development of the advanced nuclear materials-

Technical Report:

Abstract

The melting and casting parameters has been investigated for obtaining the proper U-Zr alloy. So a sound alloy ingot was sucessfully prepared. The Zr yield with the respected to the charged raw material is about 85%. The Zr content variation along the ingot is {+-} 0.2 wt%. At that time the melt was hold for three minutes at 1600 deg C. The microstructure of U-Zr ingot has been found to consist of {alpha} U as a matrix and {delta}-UZr{sub 2} as a coarse dispersion in the matrix. Additionally the U-Zr melt was rapidly solidified into powder by utilizing centrifugal atomizer. This powder tends to form fine and homogeneous microstructure. (Author).
Authors:
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1346/93
Reference Number:
SCA: 360101; 360102; PA: AIX-26:009650; EDB-95:029147; SN: 95001323249
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
36 MATERIALS SCIENCE; LIQUID METAL FUELS; URANIUM ALLOYS; ZIRCONIUM; CASTING; MICROSTRUCTURE; POWDERS; VACUUM MELTING; 360101; 360102; PREPARATION AND FABRICATION; STRUCTURE AND PHASE STUDIES
OSTI ID:
10111274
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612020; TRN: KR9400182009650
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
149 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kang, Young Ho, Lee, Kang Il, Kim, Chang Kyu, Joo, Jea Oh, Lee, Chang Tak, Park, Hee Dea, Kim, Ki Hwan, Hwang, Sung Chan, Kim, Jung Do, Ann, Hyun Suk, Chang, Sae Jung, and Joo, Keun Sik. Development of metallic fuel materials -Development of the advanced nuclear materials-. Korea, Republic of: N. p., 1994. Web.
Kang, Young Ho, Lee, Kang Il, Kim, Chang Kyu, Joo, Jea Oh, Lee, Chang Tak, Park, Hee Dea, Kim, Ki Hwan, Hwang, Sung Chan, Kim, Jung Do, Ann, Hyun Suk, Chang, Sae Jung, & Joo, Keun Sik. Development of metallic fuel materials -Development of the advanced nuclear materials-. Korea, Republic of.
Kang, Young Ho, Lee, Kang Il, Kim, Chang Kyu, Joo, Jea Oh, Lee, Chang Tak, Park, Hee Dea, Kim, Ki Hwan, Hwang, Sung Chan, Kim, Jung Do, Ann, Hyun Suk, Chang, Sae Jung, and Joo, Keun Sik. 1994. "Development of metallic fuel materials -Development of the advanced nuclear materials-." Korea, Republic of.
@misc{etde_10111274,
title = {Development of metallic fuel materials -Development of the advanced nuclear materials-}
author = {Kang, Young Ho, Lee, Kang Il, Kim, Chang Kyu, Joo, Jea Oh, Lee, Chang Tak, Park, Hee Dea, Kim, Ki Hwan, Hwang, Sung Chan, Kim, Jung Do, Ann, Hyun Suk, Chang, Sae Jung, and Joo, Keun Sik}
abstractNote = {The melting and casting parameters has been investigated for obtaining the proper U-Zr alloy. So a sound alloy ingot was sucessfully prepared. The Zr yield with the respected to the charged raw material is about 85%. The Zr content variation along the ingot is {+-} 0.2 wt%. At that time the melt was hold for three minutes at 1600 deg C. The microstructure of U-Zr ingot has been found to consist of {alpha} U as a matrix and {delta}-UZr{sub 2} as a coarse dispersion in the matrix. Additionally the U-Zr melt was rapidly solidified into powder by utilizing centrifugal atomizer. This powder tends to form fine and homogeneous microstructure. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}