Spent Fuel Storage Casks intended for use at Independent Spent Fuel Storage Installations (ISFSIS) typically are evaluated during the application and review process for low-energy impacts representative of possible handling accidents including tipover events. In the past, the analyses involved in these evaluations have assumed that the casks dropped or tipped onto an unyielding surface, a conservative and simplifying assumption. Since 10 CFR Part 72`, the regulation imposed by the Nuclear Regulatory Commission (NRC), does not require this assumption, applicants are currently seeking a more realistic model for the analyses and are using analytical models which predict the effect of a cask dropping onto a reinforced concrete pad, including en...
The Department of Energy (DOE) has developed a design concept for a set of standard canisters for th...
1999PDFResearch PaperSnow, Spencer D.Morton, D. KeithWare, A. G.Rahl, Tom E.Smith, NancyIdaho Nation...
This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel ...
Spent fuel storage casks intended for use at independent spent fuel storage installations are evalua...
Twelve tests were performed at LLNL to assess loading conditions on a spent fuel casts for side drop...
Tests were performed at Sandia National Laboratories (SNL) and Lawrence Livermore National Laborator...
The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of th...
Applicants seeking a Certificate of Compliance for an Independent Spent Fuel Storage Installation (I...
A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped ...
A series of analyses were performed to assess the structural response of spent nuclear fuel dry cask...
A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped ...
A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consist...
A crush pad has been designed and analyzed to absorb the kinetic energy of an accidentally dropped s...
This paper comparatively evaluates stress-based and strain-based acceptance criteria that are sugges...
The stress-based criteria specified in ASME Section III (American Society of Mechanical Engineers, 2...
The Department of Energy (DOE) has developed a design concept for a set of standard canisters for th...
1999PDFResearch PaperSnow, Spencer D.Morton, D. KeithWare, A. G.Rahl, Tom E.Smith, NancyIdaho Nation...
This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel ...
Spent fuel storage casks intended for use at independent spent fuel storage installations are evalua...
Twelve tests were performed at LLNL to assess loading conditions on a spent fuel casts for side drop...
Tests were performed at Sandia National Laboratories (SNL) and Lawrence Livermore National Laborator...
The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of th...
Applicants seeking a Certificate of Compliance for an Independent Spent Fuel Storage Installation (I...
A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped ...
A series of analyses were performed to assess the structural response of spent nuclear fuel dry cask...
A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped ...
A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consist...
A crush pad has been designed and analyzed to absorb the kinetic energy of an accidentally dropped s...
This paper comparatively evaluates stress-based and strain-based acceptance criteria that are sugges...
The stress-based criteria specified in ASME Section III (American Society of Mechanical Engineers, 2...
The Department of Energy (DOE) has developed a design concept for a set of standard canisters for th...
1999PDFResearch PaperSnow, Spencer D.Morton, D. KeithWare, A. G.Rahl, Tom E.Smith, NancyIdaho Nation...
This paper aims to evaluate the structural dynamic responses and damage/failure of the nuclear fuel ...