... % difference. Furthermore, we found the surface curvature in the range of 0.1–20.0 mm −1 was able to be predicted using a characteristic of the output signal peak. Consequently, we confirmed the effectiveness of the developed sensor with the OWF-based sensor. BWR liquid film measurement optical...

..., BWR NOMENCLATURE " Da Lref Nu Pr Ra Acceleration due to gravity Heat transfer coefficient Thermal conductivity Thermal conductivity of a fluid phase Thermal conductivity of a solid phase Effective stagnant thermal conductivity Time Position vector Velocity vector Pressure Forchheimer coefficient...

... Abstract The work on the understanding of the accident progression at the units of the Fukushima Dai-Ichi Nuclear Power Plant (1F) is ongoing. This contribution gives a part of detailed investigations of the control blade melt propagation downwards through the prototypic BWR bundle assembly...

... to avoid the probability of severe accident. MAAP5 break size LOCA BWR Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-65413 THE EVALUATION OF BREAK SIZES OF LOCA BY THE TEMPERATURE DIFFERENCE AT THE RECIRCULATION...

... Abstract The current severe accident management measure for Boiling Water Reactors (BWRs) in Japan adopts pre-flooding of the drywell (D/W) floor when the reactor pressure vessel (RPV) is expected to fail to prevent failure of the primary containment vessel (PCV) (wet cavity strategy...

.... MAAP5 break size LOCA BWR IDENTIFY THE BROKEN LOOP AND BREAK SIZES OF RECIRCULATION LINE LOCA FOR A BWR6/MARK PLANT Sheng-Dih Hwang, Te-Chuan Wang Division of Nuclear Engineering Institute of Nuclear Energy Research Atomic Energy Council, R.O.C. ABSTRACT In this study, the MAAP5 code was used...

... Severe Accident Isolation Condenser BWR Fukushima Daiichi Nuclear Power Station The 2011 off the Pacific coast of Tohoku Earthquake occurred on March 11. The earthquake attacked the Fukushima Daiichi nuclear power station with six boiling water reactors (BWRs), three out of which, units...

... 1-D numerical calculations of radiolysis gas detonation and mechanical response of a 12.5-m long BWR exhaust pipe have been performed. To reproduce one of scenarios of steam condensation with following radiolysis gas accumulation in an exhaust pipe initially filled with nitrogen at an initial...

... Knowing the predicted overpressure rate under anticipated operational occurrences (AOOs) is very important when evaluating the integrity of a BWR reactor pressure vessel. One of the factors that influence the overpressure rate is the wall condensing performance. Many condensing studies have been...

... BWR Modular Reactor Natural Circulation Long Cycle Hull Structure PCCS GDCS IVR Passive Safety Factory Fabrication LSBWR (Long operating cycle Simplified BWR) is a modular, direct cycle, light water cooled, and small power (100–300MWe) reactor. The design considers requirements...

... THALES-2 BWR Source Terms MARK-II Severe Accident Containment Failure Mode Containment Failure Location The THALES-2 code is an integrated severe accident analysis code developed at the Japan Atomic Energy Research Institute in order to simulate the accident progression and transport...

... 05 03 2009 Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part...

... 05 03 2009 Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part...

... by various coating methods will be discussed. BWR ECP protective insulated coatings plasma spray YSZ zircaloy Zr she Proceedings of ICONE12 12th International Conference on Nuclear Engineering April 25-29, 2004, Arlington, Virginia USA 1. INTRODUCTION IGSCC of sensitized SS components...

... Surface wettability Contact angle Thermal characteristics Temperature dependence BWR This paper presents an experimental study of surface wettability on a stainless plate in a high-temperature, high-pressure environment. Using a pressure vessel, we measured contact angles of water...

... and a simplified BWR configuration with comprehensive safety features. The Compact Containment Boiling Water Reactor (CCR), which is being developed with matured BWR technologies together with innovative systems/components, will provide attractiveness for the energy market in the world due to its flexibility...

... 17 09 2008 The reactor concept considered in this paper has a mid/small power output, a compact containment and a simplified BWR configuration with comprehensive safety features. Compact Containment BWR (CCR) is being developed with matured BWR technologies together with innovative...