Entropy-controlled BCC alloy having strong resistance to high-temperature neutron radiation damage

Patent metadata

Field	Value
Publication number	US-11111565-B2
Application number	US-201615146151-A
Country	US
Kind code	B2
Filing date	May 4, 2016
Priority date	May 4, 2015
Publication date	Sep 7, 2021
Grant date	Sep 7, 2021

Abstract

Disclosed is an entropy-controlled solid solution matrix BCC alloy having strong resistance to high-temperature neutron radiation damage. The entropy-controlled solid solution matrix BCC alloy includes three or more multicomponent main elements selected from the element group consisting of Zr, Al, Nb, Mo, Cr, V, and Ti selected based on a neutron absorption cross-sectional area and a mixing enthalpy. Each of the elements is included in an amount of 5 to 35 at %, and the entropy-controlled solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy in a medium-entropy to high-entropy state. In this invention, damage caused by neutron radiation is reduced, and entropy is controlled to thus ensure a solid solution matrix BCC structure having a slow diffusion speed, and accordingly, resistance to void swelling due to radioactive rays is high.

First claim

What is claimed is:

1. A solid solution matrix BCC alloy consisting of:
five elements selected from an element group consisting of Zr, Al, Nb, Mo, V, and Ti, selected based on a neutron absorption cross-sectional area and a mixing enthalpy,
wherein four elements of the five elements are Zr, Al, Nb and Ti in the element group,
wherein one element of the five elements is Mo or V in the element group, and
wherein each of the five elements is included at an equiatomic ratio within an error tolerance limit of 10 at % and the solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy, which includes multicomponent main elements.

2. The solid solution matrix BCC alloy of claim 1 , wherein the one element is Mo in the element group.

3. A fast-breeder reactor comprising:
the solid solution matrix BCC alloy of claim 1 as a material for a portion on which neutrons are radiated at a temperature.

4. A method of manufacturing the solid solution matrix BCC alloy of claim 1 , the method comprising:
an arc-melting step of arc-melting raw materials and then cooling the molten raw materials, or a sintering step of manufacturing the raw materials in a powder form and then sintering the raw materials using spark plasma sintering or hot isostatic pressing at a temperature and a pressure.

5. The method of claim 4 , wherein a T 2nd /T s value, which is obtained by normalizing a precipitation temperature T 2nd of a second phase competing with a solid solution using a solidification temperature T s , is used to evaluate whether or not the solid solution matrix BCC alloy is formed during preparation of the raw materials.

6. The method of claim 5 , wherein whether a single BCC-phase alloy is formed or not is evaluated based on the T 2nd /T s value of 0.65 or less.

Assignees

• Seoul Nat Univ R&Db Foundation
• Korea Inst Sci & Tech

Inventors

• Park Eun Soo
• Oh Hyun Seok
• Kim Il Hwan
• Chang Hye Jung
• Kim Sangjun
• Ryu Chae Woo

Classifications

• B22F3/105

  by using electric current {other than for infrared radiant energy}, laser radiation or plasma (B22F3/11 takes precedence){; by ultrasonic bonding (B22F3/115 takes precedence)} · CPC title

• G21C1/02

  Fast fission reactors, i.e. reactors not using a moderator {; Metal cooled reactors; Fast breeders} · CPC title

• C22C21/00

  Alloys based on aluminium · CPC title

• G21C3/07

  characterised by their material, e.g. alloys · CPC title

• C22C1/02

  by melting {(C22C1/1036 takes precedence)} · CPC title