Author: Takashi TsukadaPublisher:
ISBN:
Category :
Languages : ja
Pages : 187
Book Description
Irradiation assisted stress corrosion cracking of austenitic stainless steels
Author: Takashi TsukadaIrradiation-assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments
Author: Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 0
Book Description
Irradiation-assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments
Author: Y. ChenPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 89
Book Description
Irradiation-assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals
Author: Irradiation-assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels Irradiated in the Halden Reactor
Author: H. M. ChungPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 30
Book Description
Irradiation-assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals
Author: H. M. ChungDeposits near Medicine Hat, Alberta, Canada
Author: Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations
Author: Y. ChenPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 48
Book Description
This work is an ongoing effort at Argonne National Laboratory on the mechanistic study of irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors.
IRRADIATION-ASSISTED STRESS CORROSION CRACKING OF MODEL AUSTENITIC STAINLESS STEELS IRRADIATED IN THE HALDEN REACTOR... NUREG/CR-5608... U.S. NUCLEAR REGULATORY Commission
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Author: Jeremy Todd Busby