File Download

There are no files associated with this item.

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)
Related Researcher

김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Effect of heat flux on the structural and chemical characteristics of fuel CRUD under pressurized water reactor primary water conditions

Author(s)
Lee, YunjuHam, JunhyukYoo, Seung ChangSong, InyoungJeong, JunhyukKim, Ji Hyun
Issued Date
2025-08
DOI
10.1016/j.pnucene.2025.105802
URI
https://scholarworks.unist.ac.kr/handle/201301/87145
Citation
PROGRESS IN NUCLEAR ENERGY, v.186, pp.105802
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
ISSN
0149-1970
Keyword
COOLANTCORROSION PRODUCTPWRDEPOSITSCHEMISTRY

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.