Author: Richard J. Burian
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 82
Book Description
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing an average uranium burnup of between 1 and 2 at.%. The rate of decay heat generation was evaluated by temperature monitoring of the shipping-cask coolant. Temperatures of the fuel-element-box assembly and the fuel plates were measured with thermocouples and tempilstiks. Structurally, the fuel-element assembly was affected very little by either radiation or the organic coolant-moderator. Although there was some distortion in the side and end plates of the assembly, the coolant channels between the fuel plates were free from major fouling and obstructions. The channel cross sections were reduced at specific points less than 5 per cent. The plates studied were subjected to complete gamma scanning. Specimens removed from selected areas of the scanned plates were radiochemically analyzed for burnup and the results correlated with the gamma-scan data. Burnup profiles were constructed for each of the scanned plates. The gamma-scan data were also utilized to determine the average plate burnup. (auth).
Postirradiation Examination and Evaluation of an OMRE Fuel Assembly
Author: Richard J. Burian
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 82
Book Description
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing an average uranium burnup of between 1 and 2 at.%. The rate of decay heat generation was evaluated by temperature monitoring of the shipping-cask coolant. Temperatures of the fuel-element-box assembly and the fuel plates were measured with thermocouples and tempilstiks. Structurally, the fuel-element assembly was affected very little by either radiation or the organic coolant-moderator. Although there was some distortion in the side and end plates of the assembly, the coolant channels between the fuel plates were free from major fouling and obstructions. The channel cross sections were reduced at specific points less than 5 per cent. The plates studied were subjected to complete gamma scanning. Specimens removed from selected areas of the scanned plates were radiochemically analyzed for burnup and the results correlated with the gamma-scan data. Burnup profiles were constructed for each of the scanned plates. The gamma-scan data were also utilized to determine the average plate burnup. (auth).
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 82
Book Description
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing an average uranium burnup of between 1 and 2 at.%. The rate of decay heat generation was evaluated by temperature monitoring of the shipping-cask coolant. Temperatures of the fuel-element-box assembly and the fuel plates were measured with thermocouples and tempilstiks. Structurally, the fuel-element assembly was affected very little by either radiation or the organic coolant-moderator. Although there was some distortion in the side and end plates of the assembly, the coolant channels between the fuel plates were free from major fouling and obstructions. The channel cross sections were reduced at specific points less than 5 per cent. The plates studied were subjected to complete gamma scanning. Specimens removed from selected areas of the scanned plates were radiochemically analyzed for burnup and the results correlated with the gamma-scan data. Burnup profiles were constructed for each of the scanned plates. The gamma-scan data were also utilized to determine the average plate burnup. (auth).
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1276
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1276
Book Description
Progress Relating to Civilian Applications During ...
Author:
Publisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 94
Book Description
Publisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 94
Book Description
List
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 564
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 564
Book Description
Reprocessing of Coated OMRE Fuel
Author: L. A. Decker
Publisher:
ISBN:
Category : Organic moderated reactors
Languages : en
Pages : 26
Book Description
Publisher:
ISBN:
Category : Organic moderated reactors
Languages : en
Pages : 26
Book Description
Progress Relating to Civilian Applications During March, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 96
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 96
Book Description
Civilian Power Reactor Program
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear industry
Languages : en
Pages : 100
Book Description
Publisher:
ISBN:
Category : Nuclear industry
Languages : en
Pages : 100
Book Description
IDO
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 76
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 76
Book Description
Evaluation of Irradiated OMRE Fuel Elements First Core Loading
Author: J. H. Walter (Nuclear scientist)
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 64
Book Description
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 64
Book Description
Civilian Power Reactor Program: Addendum. Core parameter studies for selected reactor types
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 386
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 386
Book Description