This work focuses on the design, improvements, and manufacturing of a new fuel handling tool for the open-pool 2MW research reactor located at the Rhode Island Nuclear Science Center (RINSC). The reactor pool is 32-feet deep with the top of the core approximately 25 feet under water. The overhead clearance from the surface of the reactor to the roof is approximately 20 feet. Reactor operators use the fuel handling tool to remove and place in-core nuclear fuel and reflector elements, and to rotate the fuel elements to optimize the core configuration for burnup. Because of the pool depth and overhead clearance dimensions, the pole must extend to a length of 40 feet but collapse into a length of 20 feet for transportation inside the building a...
Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of ...
Prototype fast breeder reactor is U-PuO<SUB>2</SUB> fueled sodium cooled pool type fast reactor and ...
The report provides a summary of the design of the canister for final disposal of Finnish spent nucl...
Operational experience at the SRE and evaluation of alternate methods resulted in the development of...
The reactor refuelling system provides the means of transporting, storing, and handling reactor core...
The purpose of this document is to provide the design support information for the Vertical Fuel Hand...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Thesis (Ph.D. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2005.The PBMR ...
A developmental program was conducted to provide a loop facility for use in evaluating fuel specimen...
International audienceA large majority of the nuclear fuels used for CEA research (from experimental...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
Remotely operated underwater tool systems designed to operate in Nuclear Fuel Storage Basins can be ...
A Reactor Pressure Vessel Removal Feasibility Study was prepared for use in the decommissioning plan...
Graduation date: 2009In order to address the energy needs of developing countries and remote communi...
In Lithuania, all spent nuclear fuel (SNF) resulted from the operation of the Ignalina Nuclear Power...
Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of ...
Prototype fast breeder reactor is U-PuO<SUB>2</SUB> fueled sodium cooled pool type fast reactor and ...
The report provides a summary of the design of the canister for final disposal of Finnish spent nucl...
Operational experience at the SRE and evaluation of alternate methods resulted in the development of...
The reactor refuelling system provides the means of transporting, storing, and handling reactor core...
The purpose of this document is to provide the design support information for the Vertical Fuel Hand...
DESIGN OF DRY CASK STORAGE FOR SERPONG MULTI PURPOSE REACTOR SPENT NUCLEAR FUEL. The spent nuclear f...
Thesis (Ph.D. (Mechanical Engineering))--North-West University, Potchefstroom Campus, 2005.The PBMR ...
A developmental program was conducted to provide a loop facility for use in evaluating fuel specimen...
International audienceA large majority of the nuclear fuels used for CEA research (from experimental...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
Remotely operated underwater tool systems designed to operate in Nuclear Fuel Storage Basins can be ...
A Reactor Pressure Vessel Removal Feasibility Study was prepared for use in the decommissioning plan...
Graduation date: 2009In order to address the energy needs of developing countries and remote communi...
In Lithuania, all spent nuclear fuel (SNF) resulted from the operation of the Ignalina Nuclear Power...
Effective implementation of the Safeguards-by-Design (SBD) approach can help meet the challenges of ...
Prototype fast breeder reactor is U-PuO<SUB>2</SUB> fueled sodium cooled pool type fast reactor and ...
The report provides a summary of the design of the canister for final disposal of Finnish spent nucl...