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List of results

• ML22152A165  + (Assessment of Origen Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark)
• ML20203C129  + (Assessment of POST-CRITICAL-HEAT Flux Models with Lehigh Nonequilibrium Data)
• ML20045G144  + (Assessment of PWR Steam Generator Modelling in RELAP5/MOD2)
• ML20216J285  + (Assessment of Performance Issues Related to Alternate Engineered Barrier Sys Matls & Design Options)
• ML25090A245  + (Assessment of Physical Security Modeling and Simulation in the Vulnerability Assessment Process)
• ML20237H987  + (Assessment of Plant Completion & Operational Readiness for South Texas Project,Unit 1)
• ML20215N902  + (Assessment of Polyethylene as Matl for Use in High Integrity Containers. App E Withheld)
• ML20235G710  + (Assessment of Polyethylene as Matl for Use in High Integrity Containers)
• ML20195G623  + (Assessment of Polyethylene as Matl for Use in High Integrity Containers)
• ML20040C535  + (Assessment of Positron Annihilation as a NON-DESTRUCTIVE Examination Technique)
• ML20054K488  + (Assessment of Possible Amplification.Original Spectra Recommended for Facility Still Appropriate)
• ML20072L681  + (Assessment of Postulated Degraded Core Accidents in Grand Gulf Reactor Plant, Draft Informal Rept)
• ML20135D025  + (Assessment of Potential Impact of Diffusion Flames on AP600 Containment Wall & Penetrations)
• ML20132G086  + (Assessment of Potential Likelihood of Economically Producible Hydrocarbons Located Beneath South Texas Project Site)
• ML25205A073  + (Assessment of Potential Variability in Dose Exceedance Distance Calculations)
• ML20083B473  + (Assessment of Potential for ISLOCA at Davis-Besse Nuclear Power Station, Draft Rept)
• ML20248D049  + (Assessment of Potential for Liquefaction & Permanent Ground Displacements at Designated Facilities,Oyster Creek Nuclear Generating Station)
• ML20205E068  + (Assessment of Pressurized Water Reactor Primary System Leaks)
• ML20079A185  + (Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking)
• ML20058J682  + (Assessment of Probability of Damage to Core of VVER-1000 Reactor Upon Loss of Electrical Power to Power Unit)
• ML20054K820  + (Assessment of Probability of Overcooling Transients at Nuclear Plants w/C-E Nsss)
• ML20214H088  + (Assessment of Proposed Fuel Surveillance Program for Fort St Vrain)
• ML18089A266  + (Assessment of Pse&G Operations QA Program for Salem Generating Stations,Units 1 & 2)
• ML20016A409  + (Assessment of RAI Responses on the New Rifle Processing Site Gcap)
• ML20206T969  + (Assessment of RELAP/MOD2,CYCLE 36,AGAINST FIX-II Split Break Experiment No. 3027)

• ML19211D489  + (Assessment of RELAP4/MOD6)

• ML20210M461  + (Assessment of RELAP5/MOD2 Against Critical Flow Data from Tests JIT 11 and CFT 21)
• ML20046D030  + (Assessment of RELAP5/MOD2 Against ECN-REFLOOD Experiments)
• ML20096C716  + (Assessment of RELAP5/MOD2 Against Natural Circulation Experiments Performed with the REWET-III Facility)
• ML20045B852  + (Assessment of RELAP5/MOD2 Against a 10% Load Rejection Transient from 75% Steady State in the Vandellos II Nuclear Power Plant)
• ML20045J005  + (Assessment of RELAP5/MOD2 Against a Load Rejection from 100% to 50% Power in the Vandellos II Nuclear Power Plant)
• ML20062M168  + (Assessment of RELAP5/MOD2 Against a Main Feedwater Turbopump Trip Transient in the Vandellos II Nuclear Power Plant)
• ML20046D200  + (Assessment of RELAP5/MOD2 Against a Natural Circulation Experiment in Nuclear Power Plant Borssele)
• ML20045E839  + (Assessment of RELAP5/MOD2 Against a Pressurizer Spray Valve Inadverted Fully Opening Transient and Recovery by Natural Circulation in Jose Cabrera Nuclear Station)
• ML20045B966  + (Assessment of RELAP5/MOD2 Against a Turbine Trip from 100% Power in the Vandellos II Nuclear Power Plant)
• ML20042E927  + (Assessment of RELAP5/MOD2 Code Using Loss of Offsite Power Transient Data of Knu 1 Plant)
• ML20045D581  + (Assessment of RELAP5/MOD2 Computer Code Against the Net Load Trip Test Data from YONG-GWANG,UNIT 2)
• ML20045D557  + (Assessment of RELAP5/MOD2 Computer Code Against the Natural Circulation Test Data from YONG-GWANG Unit 2)
• ML20097B399  + (Assessment of RELAP5/MOD2 Critical Flow Model Using Marviken Test Data 15 and 24)
• ML20094N366  + (Assessment of RELAP5/MOD2 Cycle 36.04 Against the LOVIISA-2 STUCK-OPEN Turbine BY-PASS Valve Transient on September 1, 1981)
• ML20056B088  + (Assessment of RELAP5/MOD2 Cycle 36.04 Against Loft Small Break Experiment L3-6)
• ML20096C695  + (Assessment of RELAP5/MOD2 Cycle 36.04 Using Loft Intermediate Break Experiment L5-1)
• ML20042E920  + (Assessment of RELAP5/MOD2 Cycle 36.04 Using Loft Large Break Experiment L2-5)
• ML20096D075  + (Assessment of RELAP5/MOD2 Cycle 36.04 with Loft Large Break Loce L2-3)
• ML20097B362  + (Assessment of RELAP5/MOD2 Using Loce Large Break LOSS-OF- Coolant Experiment L2-5)
• ML20097B352  + (Assessment of RELAP5/MOD2 Using Semiscale Large Break LOSS- OF-COOLANT Experiment S-06-3)
• ML20101P867  + (Assessment of RELAP5/MOD2 Using Semiscale Intermediate Break LOSS-OF-COOLANT Experiment S-IB-3)
• ML20045C429  + (Assessment of RELAP5/MOD2 Using the Test Data of REWET-II Reflooding Experiment Sgi/R)
• ML20105D021  + (Assessment of RELAP5/MOD2, Cycle 36.02, Using Neptun Reflooding Experimental Data)
• ML20248A480  + (Assessment of RELAP5/MOD2, Cycle 36.04 Against FIX-II Guillotine Break Experiment No. 5061)
• ML19324B248  + (Assessment of RELAP5/MOD2, Cycle 36.04 Against FIX-II Split Break Experiment No. 3051)