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A list of all pages that have property "Title" with value "Predicting Pipe Rupture Frequencies Using Xlpr". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML22166A350  + (Predicting Pipe Rupture Frequencies Using Xlpr)
  • ML24326A231  + (Predicting Rupture Pressure and Leak Rate of Alloy 600 Tubes with ODSCC and Comparing with Test Results)
  • ML20149H493  + (Predicting the Pressure Driven Flow of Gases Through MICRO- Capillaries and MICRO-ORIFICES)
  • ML20088A118  + (Prediction and Experiment Comparisons for German Standard Problem 4A:PIPING Response to Blowdown)
  • ML20235L741  + (Prediction and Mitigation of EROSIVE-CORROSIVE Wear in Secondary Piping Systems of Nuclear Power Plants)
  • ML18215A297  + (Prediction in Geoenvironmental Engineering: Recommendations for Reliable Predictive Modeling)
  • ML20195D829  + (Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems)
  • ML20059D343  + (Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems - Wear and Impact Tests.Final Report,September 1988 - April 1990)
  • ML20134K597  + (Prediction of Environmentally Assisted Cracking in Bwrs: Part I:Unirradiated Stainless Steel Components)
  • ML20087P060  + (Prediction of FAR-FIELD Subsurface Radionuclide Dispersion Coefficients from Hydraulic Conductivity Measurements.A Multidimensional Stochastic Theory with Application to Fractured Rocks)
  • ML19345B783  + (Prediction of Fftf Natural Circulation Test Results Using Clinch River Breeder Reactor Plant Project Methodology)
  • ML19257B780  + (Prediction of Net Radon Emission from Model Open Pit U Mine)
  • ML20097D342  + (Prediction of Nonlinear Structural Response in LMFBR ELEVATED-TEMPERATURE Piping)
  • ML20141A132  + (Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr)
  • ML20209E979  + (Prediction of Pool Void Fraction by New Drift Flux Correlation)
  • ML20210L745  + (Predictions of J-R Curves with Large Crack Growth from Small Specimen Data)
  • ML20134G167  + (Predictions of Structural Integrity of Steam Generator Tubes Under Normal Operating Accident & Severe Accident Conditions, Presented at 24th Water Reactor Safety Meeting on 961021-23 in Bethesda,Md)
  • ML20210P454  + (Predictive Geochemical Modeling of Containment Concentrations in Laboratory Columns and in Plumes Migrating from Uranium Mill Tailings Waste Impoundments. Final Report)
  • ML20077R494  + (Predictive Geochemical Modeling of Interactions Between Uranium Mill Tailings Solutions and Sediments in a FLOW-THROUGH System.Model Formulations and Preliminary Results)
  • ML20147H512  + (Predictive Response Computations for Vibration Tests & Earthquake of 860520 Using Axisymmetric Finite Element Formulation Based on Complex Response Method & Comparison W/ Measurements-Swiss Contribution)
  • ML20246L880  + (Predictive Section 316(a) Demonstration for Alternative Winter Thermal Discharge Limit for Sequoyah Nuclear Plant, Chickamauga Reservoir,Tn)
  • ML20071D950  + (Predictor Display Concepts for Use in Nuclear Plant Control)
  • ML20077H090  + (Predismantling (Post-Fuel Removal) Surface Contamination Survey of AGN-201 Reactor & Facility)
  • ML20134A637  + (Predocketing QA Insp Rept 503/74-01 on 740725-25.No Deficiencies Noted.Major Area Inspected:Qa Program)
  • ML20136B238  + (Predocketing QA Insp Rept P-506/74-01 on 740605-07.Procedure for Engineering & Design Activities Not Formalized & Procedures for Design Changes That Originate from Licensing Review Nonexistent)
  • ML063280025  + (Preemptive Weld Overlays (Pwol) on Alloy 600 Pressurizer Nozzle-to-Pipe Welds and Associated Alternative Repair Techniques - Generic Request for Relief G-RR-1 - Supplemental Information (TAC No. MD2381 & MD2382))