This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information ...
A dry storage for RBMK spent fuel is under construction at the Ignalina site in Lithuania. Spent fue...
The management of highly radioactive spent nuclear fuel (SNF) has always been a key topic in nuclear...
The objective of this study was to determine the maximum number of specialized repository waste pack...
ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) regulates the storage of used nuclear fuel, wh...
The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in ...
This report summarizes the results of fuel integrity surveillance determined from gas sampling durin...
The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nucl...
The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spe...
This report summarizes the histories of 17 Zircaloy-clad spent fuel assemblies used in dry storage t...
The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SN...
Storage, transportation and disposal of spent nuclear fuel continue to be significant problems faced...
This report contains an evaluation of the storage conditions required for several key components and...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
The U.S. Department of Energy (DOE) has committed to provide funding to the Idaho National Laborator...
Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reacto...
A dry storage for RBMK spent fuel is under construction at the Ignalina site in Lithuania. Spent fue...
The management of highly radioactive spent nuclear fuel (SNF) has always been a key topic in nuclear...
The objective of this study was to determine the maximum number of specialized repository waste pack...
ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) regulates the storage of used nuclear fuel, wh...
The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in ...
This report summarizes the results of fuel integrity surveillance determined from gas sampling durin...
The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nucl...
The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spe...
This report summarizes the histories of 17 Zircaloy-clad spent fuel assemblies used in dry storage t...
The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SN...
Storage, transportation and disposal of spent nuclear fuel continue to be significant problems faced...
This report contains an evaluation of the storage conditions required for several key components and...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
The U.S. Department of Energy (DOE) has committed to provide funding to the Idaho National Laborator...
Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reacto...
A dry storage for RBMK spent fuel is under construction at the Ignalina site in Lithuania. Spent fue...
The management of highly radioactive spent nuclear fuel (SNF) has always been a key topic in nuclear...
The objective of this study was to determine the maximum number of specialized repository waste pack...