Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An evaluation was made of the performance of 74 helium-bonded uranium-plutonium carbide fuel elements that were irradiated in EBR-II at 38-96 kW/m to 2-12 at. percent burnup. Only 38 of these elements have completed postirradiation examination. The higher failure rate found in fuel elements which contained high-density (greater than 95 percent theoretical density) fuel than those which contained low-density (77-91 percent theoretical density) fuel was attributed to the limited ability of the high-density fuel to swell into the void space provided in the fuel element. Increasing cladding thickness and original fuel-cladding gap size were both found to influence the failure rates for elements containing low-density fuel. Lower cladding strain and higher fission-gas release were found in high-burnup fuel elements having smear densities of less than 81 percent. Fission-gas release was usually less than 5 percent for high-density fuel, but increased with burnup to a maximum of 37 percent in low-density fuel. Maximum carburization in elements attaining 5-10 at. percent burnup and clad in Types 304 or 316 stainless steel and Incoloy 800 ranged from 36-80 .mu.m and 38-52 .mu.m, respectively. Strontium and barium were the fission products most frequently found in contact with the cladding but no penetration of the cladding by uranium, plutonium, or fission products was observed.
Postirradiation Results and Evaluation of Helium-bonded Uranium--plutonium Carbide Fuel Elements Irradiated in EBR-II. Interim Report. [LMFBR].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An evaluation was made of the performance of 74 helium-bonded uranium-plutonium carbide fuel elements that were irradiated in EBR-II at 38-96 kW/m to 2-12 at. percent burnup. Only 38 of these elements have completed postirradiation examination. The higher failure rate found in fuel elements which contained high-density (greater than 95 percent theoretical density) fuel than those which contained low-density (77-91 percent theoretical density) fuel was attributed to the limited ability of the high-density fuel to swell into the void space provided in the fuel element. Increasing cladding thickness and original fuel-cladding gap size were both found to influence the failure rates for elements containing low-density fuel. Lower cladding strain and higher fission-gas release were found in high-burnup fuel elements having smear densities of less than 81 percent. Fission-gas release was usually less than 5 percent for high-density fuel, but increased with burnup to a maximum of 37 percent in low-density fuel. Maximum carburization in elements attaining 5-10 at. percent burnup and clad in Types 304 or 316 stainless steel and Incoloy 800 ranged from 36-80 .mu.m and 38-52 .mu.m, respectively. Strontium and barium were the fission products most frequently found in contact with the cladding but no penetration of the cladding by uranium, plutonium, or fission products was observed.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An evaluation was made of the performance of 74 helium-bonded uranium-plutonium carbide fuel elements that were irradiated in EBR-II at 38-96 kW/m to 2-12 at. percent burnup. Only 38 of these elements have completed postirradiation examination. The higher failure rate found in fuel elements which contained high-density (greater than 95 percent theoretical density) fuel than those which contained low-density (77-91 percent theoretical density) fuel was attributed to the limited ability of the high-density fuel to swell into the void space provided in the fuel element. Increasing cladding thickness and original fuel-cladding gap size were both found to influence the failure rates for elements containing low-density fuel. Lower cladding strain and higher fission-gas release were found in high-burnup fuel elements having smear densities of less than 81 percent. Fission-gas release was usually less than 5 percent for high-density fuel, but increased with burnup to a maximum of 37 percent in low-density fuel. Maximum carburization in elements attaining 5-10 at. percent burnup and clad in Types 304 or 316 stainless steel and Incoloy 800 ranged from 36-80 .mu.m and 38-52 .mu.m, respectively. Strontium and barium were the fission products most frequently found in contact with the cladding but no penetration of the cladding by uranium, plutonium, or fission products was observed.
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 724
Book Description
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 724
Book Description
ERDA Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 716
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 716
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 724
Book Description
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 724
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1322
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1322
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 912
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 912
Book Description
Advanced LMFBR Fuels
Author: Joseph Leary
Publisher:
ISBN:
Category : Liquid metal fast breeder reactor
Languages : en
Pages : 722
Book Description
Publisher:
ISBN:
Category : Liquid metal fast breeder reactor
Languages : en
Pages : 722
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1744
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1744
Book Description
Topical Meeting Proceedings, Monterey, California, March 5-8, 1979
Author: E. C. Norman
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 1010
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 1010
Book Description
INIS Atomindeks
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 806
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 806
Book Description