Call Number (LC) Title Results
E 1.99:fcrd-nfst--2013-000263 Spent Nuclear Fuel and High-Level Radioactive Waste Inventory Report 1
E 1.99:fcrd-nfst-2013-000263 SPENT NUCLEAR FUEL AND REPROCESSING WASTE INVENTORY.
NUCLEAR FUELS STORAGE AND TRANSPORTATION PLANNING PROJECT INVENTORY BASIS
SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE INVENTORY REPORT
3
E 1.99:FCRD-NFST-2014-000602-Rev.3 Dry Storage Cask Inventory Assessment 1
E 1.99: fcrd-- nfst-2016-000478 Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites 1
E 1.99:fcrd-ufd-2012-000142 Benchmarking a new closed-form thermal analysis technique against a traditional lumped parameter, finite-difference method 1
E 1.99: fcrd-ufd--2013-000135 Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport - Modeling, Simulation and Experimental Integration RD&D Plan 1
E 1.99:fcrd-ufd-2013-000294 anl-13/15 Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel. Rev. 1 1
E 1.99: fcrd-ufd-2013-000297 Preliminary Thermal Modeling of HI-Storm 100S-218 Version B Storage Modules at Hope Creek Cuclear Power Station ISFSI 1
E 1.99: fcrd-ufd--2013-000325 Used Nuclear Fuel Loading and Structural Performance Under Normal Conditions of Transport- Demonstration of Approach and Results on Used Fuel Performance Characterization 1
E 1.99:fcrd-ufd-2013-000401 Used Fuel Disposition Campaign - Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys 1
E 1.99:fcrd-ufd-2014-000317 PRELIMINARY REPORT EFFECTS OF IRRADIATION AND THERMAL EXPOSURE ON ELASTOMERIC SEALS FOR CASK TRANSPORTATION AND STORAGE. 1
E 1.99:fcrd-ufd--2015-000008 Effects of Lower Drying-Storage Temperatures on the DBTT of High-Burnup PWR Cladding 1
E 1.99:fcrd-ufd--2015-000533 White Paper Summary of 2nd ASTM International Workshop on Hydrides in Zirconium Alloy Cladding 1
E 1.99:fcrd-ufd-2016-000065 Effects of Lower Drying-Storage Temperature on the Ductility of High-Burnup PWR Cladding 1
E 1.99:fcrd-used-2011-000136 rev. 0 Gap Analysis to Support Extended Storage of Used Nuclear Fuel, Rev. 0 1
E 1.99:fcsne v.2.0 Fuel Cycle Services Needs Estimator v.2.0 1
E 1.99:fct Fat Crayon Toolkit 1
E 1.99:fdb50470-aa0f-4f0c-ad83-09788e4a41ea Well Leakage Analysis Tool (WLAT) Users Manual Version 2016.11-1.0.0.3. 1
E 1.99:FDD-ENG--97-0044,Rev.1 R-Reactor Disassembly Basin Radiation Survey and Sampling Plan 1
E 1.99:FDD-ENG--98-0029 Analytical Results of the 1997 R-Reactor Disassembly Basin Sampling Program 1