Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Dohee Hahn

Sung Ho Kim

Jun Hwan Kim

Chan Bock Lee

Ki-Hwan Kim

Ho Jin Ryu

Tae Kyu Kim

Jong Hyuk Baek

Seok-Jin Oh

Jin-Sik Cheon

Jong-Hyuk Baek

Seong-O Kim

Tae-Kyu Kim

Young-Mo Ko

Yoon-Myeong Woo

Byoung-Oon Lee

Jae-Hyuk Eoh

Yeong-Il Kim

Woo-Gon Kim

Woo Gon Kim

Chang Hee Han

Chong-Tak Lee

Yoon-Sub Sim

Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR).

High Cr ferritic/martensitic steels having an improved creep resistance for in-core component materials in nuclear reactor, and preparation method thereof

Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way.

Nuclear fuel rod for fast reactors with oxide coating layer on inner surface of cladding, and manufacturing method thereof

A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool. In the circular vertical tube is disposed a sodium-sodium heat exchanger, which is connected to a sodium-air heat exchanger mounted above a reactor building via a heat removing sodium loop, in such a manner that it is placed at the position higher than a liquid level of the sodium in the cold pool under the normal steady-state conditions.

Passive safety-grade decay-heat removal method and decay-heat removal system for LMR with pool direct heat cooling process

Growing community of inventors

Daejeon, South Korea

Dohee Hahn