Author: Herreng, Ertaud and Pasquet
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 46
Book Description
Description of Reactors G2 and G3
Author: Herreng, Ertaud and Pasquet
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 46
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 46
Book Description
The EBWR
Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 254
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 254
Book Description
Final Report
Author: J. W. Weber
Publisher:
ISBN:
Category :
Languages : en
Pages : 58
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 58
Book Description
Zirconium in the Nuclear Industry
Author: ASTM Committee B-10 on Reactive and Refractory Metals and Alloys
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694
Book Description
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694
Book Description
Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation
Author: J. M. Markowitz
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52
Book Description
Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding
Author: Wallace Davis
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
Book Description
Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior
Author: A. L. Geary
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 28
Book Description
Irradiation effects on fe distributions in zircaloy-2 and zr-2.5nb
Author: H. Zou
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Rd-12 is a high-pressure recirculating water loop designed to resemble the primary heat transport circuit of a candu-phw reactor. it has been used to carry out blowdown experiments in which many of the physical events that could occur during a reactor loss-of-coolant accident (loca) are simulated. data from these experiments are intended to be used to validate the computer programs used for candu reactor loca analysis. this report describes a series of inlet header blowdown experiments conducted over different periods between 1978 and 1980, during which water from a pressurized tank was injected into the loop during the blowdown. the fuel element simulators were low heat capacity and directly heated. a description of the test procedure and detailed results from four of the experiments are presented in the report. a number of observations drawn from the experimental data are also presented. a complete record of data from all tests in the series is available on magnetic tape at the chalk river nuclear laboratories, and may be accessed through the cdc-6600 system. the work described in this report was funded under the joint aecl/ontario hydro candev program.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Rd-12 is a high-pressure recirculating water loop designed to resemble the primary heat transport circuit of a candu-phw reactor. it has been used to carry out blowdown experiments in which many of the physical events that could occur during a reactor loss-of-coolant accident (loca) are simulated. data from these experiments are intended to be used to validate the computer programs used for candu reactor loca analysis. this report describes a series of inlet header blowdown experiments conducted over different periods between 1978 and 1980, during which water from a pressurized tank was injected into the loop during the blowdown. the fuel element simulators were low heat capacity and directly heated. a description of the test procedure and detailed results from four of the experiments are presented in the report. a number of observations drawn from the experimental data are also presented. a complete record of data from all tests in the series is available on magnetic tape at the chalk river nuclear laboratories, and may be accessed through the cdc-6600 system. the work described in this report was funded under the joint aecl/ontario hydro candev program.
Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5
Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water
Author: Stanley Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 34
Book Description