To ensure structural integrity during normal conditions of transport (NCT), Federal regulations in 10CFR71.71 require that the nuclear material package designs be evaluated for the effects of free drops. The vessel stress acceptance criteria for these drops are given in Regulatory Guide 7.6 and ASME Section III Code. During initial phases of the package design, the effects of the NCT free drops can be evaluated by simplified analytical solutions which will ensure that the safety margins specified in R. G. 7.6 are met. These safety margins can be verified during the final stages of the package design with dynamic analyses using finite element methods. This paper calculates the maximum impact {open_quotes}g{close_quotes} loading on the vessel...
Federal regulation (10 CFR Part 71) specifies a number of impact conditions (free-drop, penetration,...
This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental punctu...
One important part of radioactive material transport risk assessments is amount of release from pack...
This paper comparatively evaluates stress-based and strain-based acceptance criteria that are sugges...
A shipping container of fresh fuel in nuclear industry is used to prevent a leakage of unirradiated ...
The response of radioactive material transportation packages to mechanical accident loadings can be ...
In the evaluation of the safety of radioactive material transportation it is important to consider t...
The casks or packaging systems used for the transportation of nuclear materials, especially spent fu...
The stress-based criteria specified in ASME Section III (American Society of Mechanical Engineers, 2...
Shipping containers used for transporting radioactive material must be certified using federal regul...
The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package w...
This paper presents the results of the numerical analysis performed to asses the structural integrit...
The scope of the present study is to evaluate the structural response and performance in a free dro...
Packaging systems for the transportation of radioactive wastes have to be designed according to rigo...
Type B radioactive material packages are required to withstand a hypothetical puncture accident of a...
Federal regulation (10 CFR Part 71) specifies a number of impact conditions (free-drop, penetration,...
This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental punctu...
One important part of radioactive material transport risk assessments is amount of release from pack...
This paper comparatively evaluates stress-based and strain-based acceptance criteria that are sugges...
A shipping container of fresh fuel in nuclear industry is used to prevent a leakage of unirradiated ...
The response of radioactive material transportation packages to mechanical accident loadings can be ...
In the evaluation of the safety of radioactive material transportation it is important to consider t...
The casks or packaging systems used for the transportation of nuclear materials, especially spent fu...
The stress-based criteria specified in ASME Section III (American Society of Mechanical Engineers, 2...
Shipping containers used for transporting radioactive material must be certified using federal regul...
The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package w...
This paper presents the results of the numerical analysis performed to asses the structural integrit...
The scope of the present study is to evaluate the structural response and performance in a free dro...
Packaging systems for the transportation of radioactive wastes have to be designed according to rigo...
Type B radioactive material packages are required to withstand a hypothetical puncture accident of a...
Federal regulation (10 CFR Part 71) specifies a number of impact conditions (free-drop, penetration,...
This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental punctu...
One important part of radioactive material transport risk assessments is amount of release from pack...