Title:
SUPERBLY ANTI-CORROSIVE ZIRCONIUM ALLOY FOR NUCLEAR FUEL CLADDING AND METHOD FOR PRODUCING THE ZIRCONIUM ALLOY
Document Type and Number:
WIPO Patent Application WO/2016/167404
Kind Code:
A1
Abstract:
The purpose of the present invention is to provide a zirconium alloy composition having an improved anti-corrosion characteristic which can be utilized for nuclear fuel cladding and as material for nuclear structures, and a method for producing the zirconium alloy, the optimal heat treatment conditions being considered for the zirconium alloy, wherein tin which has a negative effect on corrosion resistance is completely eliminated from the zirconium alloy, and copper is added thereto after increasing molybdenum content to greater than the solid solubility threshold level. The zirconium alloy for nuclear fuel cladding according to the present invention comprises 0.5-1.2 wt% niobium, 0.4-0.8 wt% molybdenum, 0.1-0.15 wt% copper, 0.15-0.2 wt% iron, and the remainder in zirconium, and the method for producing the zirconium alloy for nuclear fuel cladding comprises: a first step of producing an ingot by dissolving a mixture of zirconium alloy composition elements; a second step for solution heat-treating the ingot produced in the first step for 30-40 minutes at 1,000-1,050℃(β) and then β-quenching by rapidly cooling in water; a third step for heating the ingot heat-treated in the second step for 20-30 minutes at 630-650℃ and then hot-rolling at a 60-65% reduction ratio; a fourth step for a first intermediate vacuum heat treatment of the rolled material hot-rolled in the third step for 3-4 hours at 570-590℃ and then cold-rolling for the first time at 30-40% reduction ratio; a fifth step for a second intermediate vacuum heat treatment of the rolled material cold-rolled for the first time in the fourth step for 2-3 hours at 560-580℃ and then cold-rolling for the second time at 50-60% reduction ratio; a sixth step for a third intermediate vacuum heat treatment of the rolled material cold-rolled for the second time in the fifth step for 2-3 hours at 560-580℃ and then cold-rolling for the third time at a 30-40% reduction ratio; and a seventh step for the final heat treatment of the rolled material cold-rolled for the third time in the sixth step.
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Inventors:
CHOI MIN YOUNG (KR)
MOK YONG KYOON (KR)
KIM YOON HO (KR)
NA YEON SOO (KR)
LEE CHUNG YONG (KR)
JANG HUN (KR)
JUNG TAE SIK (KR)
KO DAE GYUN (KR)
LEE SUNG YONG (KR)
LEE SEUNG JAE (KR)
KIM JAE IK (KR)
MOK YONG KYOON (KR)
KIM YOON HO (KR)
NA YEON SOO (KR)
LEE CHUNG YONG (KR)
JANG HUN (KR)
JUNG TAE SIK (KR)
KO DAE GYUN (KR)
LEE SUNG YONG (KR)
LEE SEUNG JAE (KR)
KIM JAE IK (KR)
Application Number:
PCT/KR2015/005319
Publication Date:
October 20, 2016
Filing Date:
May 27, 2015
Export Citation:
Assignee:
KEPCO NUCLEAR FUEL CO LTD (KR)
International Classes:
C22C16/00; B21B3/00; C22F1/18
Foreign References:
| KR20100081744A | 2010-07-15 | |||
| KR20010047592A | 2001-06-15 | |||
| US4814136A | 1989-03-21 | |||
| KR20000026542A | 2000-05-15 |
Other References:
See also references of EP 3284837A4
Attorney, Agent or Firm:
LEE, UN CHEOL (KR)
이은철 (KR)
이은철 (KR)
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