Categorical Exclusion Determinations: Idaho

Multimodal Nondestructive Dry Cask Basket Structure and Spent Fuel Evaluation- The University of Mississippi CX(s) Applied: B3.6Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

The Influences of Neutron Irradiation on Aggregate Induced Degradation of Concrete - University of California, Los Angeles CX(s) Applied: B3.6Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

Used Fuel Storage Monitoring Using Novel 4He Scintillation Fast Neutron Detectors and Neutron Energy Discrimination Analysis - University of Florida CX(s) Applied: B3.6Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

Development and Demonstration of an In-situ Tritium Scavenger - University of Wisconsin CX(s) Applied: B3.6Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

Electric Vehicle Infrastructure (EVI) Laboratory Upgrades CX(s) Applied: B1.31Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

Materials and Fuels Complex (MFC)-752 Analytical Laboratory Casting Laboratory Glovebox Heat Detection CX(s) Applied: B2.2Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

Prefabricated High-Strength Rebar Systems with High-Performance Concrete for Accelerated Construction of Nuclear Concrete Structures - University of Notre Dame CX(s) Applied: B3.6Date: 06/17/2015 Location(s): IdahoOffices(s): Nuclear Energy

Radiation-induced Swelling and Microcracking in SiC Cladding for LWRs - University of Wisconsin CX(s) Applied: B3.6Date: 06/17/2015 Location(s): IdahoOffices(s): Nuclear Energy

Creep and Creep-Fatigue Crack Growth Mechanisms in Alloy 709- North Carolina State University CX(s) Applied: B3.6Date: 06/17/2015 Location(s): IdahoOffices(s): Nuclear Energy

Mechanistic and Validated Creep/Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations - North Carolina State University CX(s) Applied: B3.6Date: 06/17/2015 Location(s): IdahoOffices(s): Nuclear Energy