The NAC-MPC: Transport Ready Canister Technology for Spent Fuel from Older Plants

 
The NAC-MPC is a "sister-system" to the UMS designed especially for particular fuel from older U.S. commercial plants. NAC designed the NAC-MPC fuel basket based on NRC-licensed fuel basket design and methodology. The system, which also uses the licensed NAC-STC transport cask design, has a capacity of up to 37 PWR or up to 89 BWR fuel assemblies. NAC developed and first licensed the NAC-MPC system for use at the Yankee nuclear facility in Rowe, Massachusetts, and for the Connecticut Yankee nuclear facility in Haddam Neck, Connecticut.
 
 
Key Features
 
  • Much like the UMS, uses a high-capacity canister-based system for storing and transporting spent nuclear fuel— the canister can be placed in storage or transport overpacks
  • Uses the NAC-STC transport cask, the first cask licensed for standard fuels by the U.S. Nuclear Regulatory Commission for both storage and transport (certificate of compliance no. 71-9235)
  • Safety of NAC-STC confirmed in rigorous drop, fire, immersion and puncture tests
  • Fuel basket in canister uses patented, licensed tube-and-disk design, like the UMS
  • Design meets storage and transport needs at older U.S. nuclear plants, which may be among the first to ship fuel to an interim DOE storage facility

 

The NAC-MPC Advantage  

 
  • Licensed transport overpack
  • Transport ready
  • Fully licensed technology
  • Ready application to older sites
  • High capacity
  • Best value, smallest footprint

NAC-MPC Applications


The NAC-MPC is compatible for storing and transporting spent fuel from many older U.S. nuclear plants, with widespread applications for U.S. government spent fuel management and worldwide.