Proceedings of the ... Workshop on Containment IntegrityU.S. Nuclear Regulatory Commission, 1986 |
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عبارات ومصطلحات مألوفة
accident sequences aerosol airmass Albuquerque analysis basemat calculations combustion components concrete containment containment atmosphere containment building containment failure containment integrity containment model containment structures coolant core melt crack deflagration direct heating displacement drywell effects elastic equations equipment hatch evaluated experimental factor failure mode failure pressure Figure finite element fission product glow plug hydrogen burn ILRT initial leakage rate liner plate load LOCA MASS POINT material maximum measured method nuclear power plants Nuclear Regulatory Commission occur Ontario Hydro overpressurization parameter penetrations performed Pressurized Water Reactor primary system RATE AND UCL reactor rebars release requirements Ringhals risk rupture safety Sandia National Laboratories seal secondary building severe accident shear shell shell model source term specimen spray steam steel strain stress Subsection IWE surface temperature thermal Type A test U. S. Nuclear Regulatory valve vent vessel breach volume wall welds
مقاطع مشهورة
الصفحة 223 - This work was supported by the US Nuclear Regulatory Commission and performed at Sandia National Laboratories, which is operated for the US Department of Energy under contract number DE-AC04-76DP00789. LITERATURE CITED 1. Hobbins, RR, CE Johnson, RA Lorenz, AR Taig, and RC Vogel, "An Overview of Fission Product Release Experiments...
الصفحة 488 - Elastic-Plastic Fracture: Second Symposium, Volume II — Fracture Resistance Curves and Engineering Applications, ASTM STP 803, CF Shih and JP Gudas, Eds., American Society for Testing and Materials, 1983, pp.
الصفحة 237 - Comitato Nazionale per la Ricerca e per lo Sviluppo dell'Energia Nucleare e delle Energie Alternative, Italy Department of Transport, United Kingdom Osterreichisches Forschungszentrum Seibersdorf GmbH, Austria Pettersson, BC Pittuck, A.
الصفحة 164 - Rules for Inservice Inspection of Nuclear Power Plant Components," of the ASME Boiler and Pressure Vessel Code.
الصفحة 168 - TESTS A. Containment inspection. A general inspection of the accessible interior and exterior surfaces of the containment structures and components shall be performed prior to any Type A test to uncover any evidence of structural deterioration which may affect either the containment structural integrity or leak-tightness. If there is evidence of structural deterioration. Type A tests shall 10 CFR Ch.
الصفحة 179 - Additionally, temperature sensing devices shall be located at different parts of the structure wherever local temperature variations might be expected in the course of the test. Fans or other means for air circulation may be used to equalize temperatures in any region where representative temperature measurements are taken and appreciable temperature variations exist. The temperature pattern revealed by the survey shall be employed in determination of the mean representative temperature for the absolute...
الصفحة 317 - ... supported by the United States Nuclear Regulatory Commission and performed at Sandia National Laboratories which is operated for the US Department of Energy under contract number DE-AC04-76DP00789 . risk or present unique challenges to the containment.
الصفحة 488 - Kumar, V., German. MD, and Shih, CF, "An Engineering Approach for Elastic Plastic Fracture Analysis," Electric Power Research Institute.