Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

The Industry & Academic Cooperation in Chungnam National University

Korea Hydro & Nuclear Power

Yoon Sang Lee

Han Soo Lee

Ho Jin Ryu

Seon Jin Kim

Jong Hyeon Lee

Seok Jin Oh

Jong Man Park

Don Bae Lee

Sun Kyo Chung

H Nersisyan Hayk

Chang Kyu Kim

Chul Gyo Seo

The manufacturing method for high-purity Zirconium is characterized by self-propagating high temperature synthesis (SHS) of a raw material having zirconium raw ore containing ZrO, ZrSiO, KZr(PO), or a mixture thereof and a reducing agent that is metal powder, to prepare zirconium intermetallic compound or zirconium nitride, followed by the recovery of high-purity Zr by electrolytic refining the reaction product of the SHS.

Eco-friendly smelting process for reactor-grade zirconium using raw ore metal reduction and electrolytic refining integrated process

A casting apparatus includes a hermetically sealed chamber, wherein the chamber includes: a melt-heating portion to melt external uranium deposits, the melt-heating portion being tiltable to allow the resulting liquid molten material to be discharged to the outside, an ingot-forming portion to receive the molten material discharged from the melt-heating portion and to cool-solidify the molten material, and a salt-capturing portion provided on the melt-heating portion, to solidify a salt gas produced when the uranium deposits are molten, and thereby recover the salt gas, wherein the ingot-forming portion includes: a horizontal turn-table rotated by an operating means, and a plurality of molds mounted on the edge of the turn-table, each containing the molten material, which is then cooled.

Ingot-casting apparatus using uranium deposits

The present invention relates to a multi-core fuel rod for research reactor and, more particularly, to a multi-core fuel rod for research reactor in which monolithic fuel cores made of uranium-molybdenum alloy are disposed in an aluminum matrix in a multi-core form. The multi-core fuel rod in accordance with the present invention provides a minimized contact surface area between nuclear fuel and aluminum, and reduces the formation of pores and swelling by restraining formation of reaction layer to avoid excessive reaction between the fuel and aluminum. Therefore, improved stability of nuclear fuel can be obtained by minimizing temperature rise as well as achieving high density and thermal conductivity of the fuel.

Multi-core fuel rod for research reactor and manufacturing method thereof

Growing community of inventors

Daejeon, South Korea

Yoon Sang Lee