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1. WO2019162876 - ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE AND SERVICE TEMPERATURE FOR USE IN THE FUEL CLADDING AND CORE STRUCTURAL PARTS OF A NUCLEAR REACTOR

Publication Number WO/2019/162876
Publication Date 29.08.2019
International Application No. PCT/IB2019/051425
International Filing Date 21.02.2019
IPC
C22C 16/00 2006.1
CCHEMISTRY; METALLURGY
22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
CALLOYS
16Alloys based on zirconium
C22F 1/18 2006.1
CCHEMISTRY; METALLURGY
22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
FCHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS OR NON-FERROUS ALLOYS
1Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
16of other metals or alloys based thereon
18High-melting or refractory metals or alloys based thereon
G21C 3/07 2006.1
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
04Constructional details
06Casings; Jackets
07characterised by their material, e.g. alloys
CPC
C22C 16/00
CCHEMISTRY; METALLURGY
22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
CALLOYS
16Alloys based on zirconium
C22F 1/186
CCHEMISTRY; METALLURGY
22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
FCHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
1Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
16of other metals or alloys based thereon
18High-melting or refractory metals or alloys based thereon
186of zirconium or alloys based thereon
G21C 3/07
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
04Constructional details
06Casings; Jackets
07characterised by their material, e.g. alloys
Y02E 30/30
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
30Energy generation of nuclear origin
30Nuclear fission reactors
Applicants
  • COMISIÓN NACIONAL DE ENERGÍA ATÓMICA (CNEA) [AR]/[AR]
  • UNIVERSIDAD NACIONAL DE GENERAL SAN MARTIN [AR]/[AR]
  • UNIVERSIDAD TECNOLÓGICA NACIONAL [AR]/[AR]
  • CONSEJO NACIONAL DE INVESTIGACIONES CIENTÍFICAS Y TÉCNICAS (CONICET) [AR]/[AR]
  • FERREIRÓS AUER, Pedro A. [ES]/[AR]
Inventors
  • FERREIRÓS AUER, Pedro A.
  • ALONSO, Paula R.
  • FORTI, Mariano D.
  • GARGANO, Pablo H.
  • KNIZNIK, Laura
  • LANZANI, Liliana A.
  • RUBIOLO, Gerardo H.
Priority Data
2018010040021.02.2018AR
Publication Language Spanish (es)
Filing Language Spanish (ES)
Designated States
Title
(EN) ZIRCONIUM ALLOYS WITH IMPROVED CORROSION RESISTANCE AND SERVICE TEMPERATURE FOR USE IN THE FUEL CLADDING AND CORE STRUCTURAL PARTS OF A NUCLEAR REACTOR
(ES) ALEACIONES DE CIRCONIO CON RESISTENCIA A LA CORROSIÓN Y TEMPERATURA DE SERVICIO MEJORADAS PARA USAR EN EL REVESTIMIENTO DEL COMBUSTIBLE Y LAS PARTES ESTRUCTURALES DEL NÚCLEO DE UN REACTOR NUCLEAR
(FR) ALLIAGES DE ZIRCONIUM PRÉSENTANT UNE RÉSISTANCE À LA CORROSION ET UNE TEMPÉRATURE DE SERVICE AMÉLIORÉES, À UTILISER SUR LE REVÊTEMENT DU COMBUSTIBLE ET LES PARTIES STRUCTURALES DU NOYAU D'UN RÉACTEUR NUCLÉAIRE
Abstract
(EN) This invention relates to alloys based on zirconium (Zr) and containing small percentages of niobium (Nb) and tantalum (Ta), which are corrosion-resistant and have a service temperature suitable for use in zones with a high neutron flux of nuclear power reactors, such as the nuclear fuel cladding and structural components of the reactor core.
(ES) La presente invención se refiere a aleaciones de circonio (Zr) con pequeños porcentajes de niobio (Nb) y tantalio (Ta), con resistencia a la corrosión y temperatura de servicio, para la utilización en zonas de elevado flujo neutrónico de los reactores nucleares tales como el revestimiento del combustible y partes estructurales del núcleo.
(FR) La présente invention concerne des alliages de zirconium (Zr) présentant de faibles pourcentages de niobium (Nb) et de tantale (Ta), possédant une résistance à la corrosion et une température de service améliorées, à utiliser dans des zones à flux neutronique élevé des réacteurs nucléaires, telles que le revêtement du combustible et les parties structurales du noyau.
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