G
Geun-Il Park
Researcher at KAERI
Publications - 35
Citations - 313
Geun-Il Park is an academic researcher from KAERI. The author has contributed to research in topics: Welding & Spent nuclear fuel. The author has an hindex of 8, co-authored 35 publications receiving 280 citations.
Papers
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Journal ArticleDOI
Current Status of Pyroprocessing Development at KAERI
Han-Soo Lee,Geun-Il Park,Jae-Won Lee,Kweon-Ho Kang,Jin-Mok Hur,Jeong-Guk Kim,Seungwoo Paek,In-Tae Kim,IL-Je Cho +8 more
TL;DR: In this article, a pyroprocessing integrated inactive demonstration facility (PRIDE) was constructed at KAERI and it began test operation in 2012 to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards related activities.
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Purification of used eutectic (LiCl–KCl) salt electrolyte from pyroprocessing
TL;DR: In this paper, the separation characteristics of surrogate rare-earth fission products in a eutectic (LiCl-KCl) molten salt were investigated using an integrated rare earth separation apparatus comprising a precipitation reactor, a solid detachment device, and a layer separation device.
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Electrolytic decomposition of ammonia to nitrogen in a multi-cell-stacked electrolyzer with a self-pH-adjustment function
TL;DR: In this article, a self-pH-adjustment function was proposed for a multi-cell-stacked electrolyzer with an anion exchange membrane, where a portion of the ammonia solution from a pH adjustment reservoir was circulated through the cathodic chambers of the electrolyzer.
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Recovery of uranium from (U,Gd)O2 nuclear fuel scrap using dissolution and precipitation in carbonate media
Kwang-Wook Kim,Jun-Taek Hyun,Eil-Hee Lee,Geun-Il Park,Kune-Woo Lee,Myung-June Yoo,Kee-Chan Song,Jei-Kwon Moon +7 more
TL;DR: In this article, a process to recover pure uranium from contaminated (U,Gd)O 2 scraps generated from nuclear fuel fabrication processes by using the dissolution of (Gd,O 2) scraps in a carbonate with H 2 O 2 and the precipitation of the dissolved uranium as UO 4.
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Fabrication and physical properties of lanthanide oxide glass wasteform for the immobilization of lanthanide oxide wastes generated from pyrochemical process
Jung-Hoon Choi,In-Hak Cho,Hee-Chul Eun,Hwan-Seo Park,Yung-Zun Cho,Ki-Rak Lee,Geun-Il Park,Song Hyun Kim,Chang-Ho Shin,Jong Kyung Kim +9 more
TL;DR: In this paper, the fabrication of a borosilicate glass based wasteform with a glass matrix of SiO2-Al2O3-B2O 3 having a high waste loading of 50% lanthanide oxide was reported.