Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20028A61430 September 1982Supplementary Manual for F0RE-2M Computer Program.Fuel cladding
Power change
ML20053D23728 May 1982SPTH3:Subroutine for Finding Shortest Sabotage Paths.
ML20053D22428 May 1982Safeguards Sys Effectiveness Modeling.
ML20049H87728 February 1982Summary Rept on Current Assessment of Natural Circulation Capability W/Heterogeneous Core.Coast down
ML20050J0529 February 1982to Crbr Requirements for Environ Qualification of Class IE Equipment.Safe Shutdown Earthquake
Post Accident Monitoring
B.5.b
ML20039G85331 December 1981Assessment of Hypothetical Core Disruptive Accident Energetics in Clinch River Breeder Reactor Project Heterogeneous Reactor Core.Hydrostatic
Fuel cladding
Power change
ML19345B79630 November 1980Clinch River Breeder Reactor Project Ncvp Pretest Prediction of Fueled Open Test Assembly Temps for Fftf Natural Circulation Test Initiated at 35% Power & 75% Flow. Input Data & Microfiche of Demo Code Program Mods Encl
ML19309F37231 January 1980Final Rept on Base Matls Tests for Cell Liner Steels.
ML19211A74914 December 1979Facility Core Assembly Hot Channel Factors Preliminary Analysis, Revision 3
ML19305D74831 October 1979Structural Response of Scale Models to Simulated Hypothetical Core Disruptive Accident. Revision 1
ML19305A78031 January 1979Predicted Steady State Thermal-Hydraulic Performance of Fuel & Blanket Assemblies in Plant Heterogeneous Core, Revision 1
ML20147D96630 November 1978Closure Head Capability for Structural Margin Beyond Design Base Loading. Results of Tests Indicate That Closure Head Is Capable of W/Standing 661 Mj Structural Margin Beyond Design Base Loads W/Out Structural Failures
ML20147D96031 October 1978Structural Response of Crbrp Scale Models to a Simulated Hypothetical Core Disruptive Accident. Primary Objective of Tests Was to Verify That Scale Models of Subj Reactor Can W/Stand Loads Resulting from Simulation of Hcda
ML20204B63831 August 1978Requirements for Environ Qualification of Class IE EquipmentSafe Shutdown Earthquake
Post Accident Monitoring
ML19270F60930 April 1978Analysis of Hypothetical Core Distruptive Events in Clinch River Breeder Reactor Plant.Shutdown Margin
ML19331D32731 January 1978Clinch River Breeder Reactor Plant Fuel Assembly Structural Analysis in Support of Final Design Review.Hydrostatic
ML20063P28231 December 1977Preliminary Analysis of Heat Generating Blockage in Crbr Fuel & Radial Blanket Assemblies to Determine Detection Requirements
ML19281A06728 February 1977WARD-D-0169, Clinch River Breeder Reactor Plant,Response of Plant to Postulated Loss of One Heat Transport Loop W/ Failure of Both Reactor Shutdown Sys. Addresses Anticipated Event Causing Most Severe Loss of Heat Removal