Description of Reactors G2 and G3

Description of Reactors G2 and G3 PDF Author: Herreng, Ertaud and Pasquet
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 46

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Description of Reactors G2 and G3

Description of Reactors G2 and G3 PDF Author: Herreng, Ertaud and Pasquet
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 46

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The EBWR

The EBWR PDF Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 254

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Final Report

Final Report PDF Author: J. W. Weber
Publisher:
ISBN:
Category :
Languages : en
Pages : 58

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Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: ASTM Committee B-10 on Reactive and Refractory Metals and Alloys
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694

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Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation

Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation PDF Author: J. M. Markowitz
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52

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Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding

Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding PDF Author: Wallace Davis
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52

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Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior

Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior PDF Author: A. L. Geary
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 28

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Irradiation effects on fe distributions in zircaloy-2 and zr-2.5nb

Irradiation effects on fe distributions in zircaloy-2 and zr-2.5nb PDF Author: H. Zou
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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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

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5 PDF Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40

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The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water

The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water PDF Author: Stanley Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 34

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