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 |