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Keyword: ABWR
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Proceedings Papers

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 105-114, July 12–16, 2009
Paper No: ICONE17-75104
... This work developed an Advanced Boiling Water Reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one...
Proceedings Papers

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 389-394, July 12–16, 2009
Paper No: ICONE17-75401
... in turbine trip and load rejection transients are met and Lungmen RETRAN model is performing well and applicable for Lungmen startup test predictions and analyses. 23 02 2010 RETRAN LUNGMEN Startup Test Turbine trip Load rejection ABWR Copyright © 2009 by ASME1 Proceedings of...
Topics: Stress, Turbines
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 1035-1044, May 11–15, 2008
Paper No: ICONE16-48955
... This work developed a stand-alone ABWR (Advanced Boiled Water Reactor) feedwater pump and controller model which was incorporated with a simplified reactor vessel and steam line model. The purpose of this work is to improve the existing model in PCTran-ABWR, a nuclear power plant (NPP...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 727-734, April 14–18, 2002
Paper No: ICONE10-22549
... For the purpose of shortening outage schedules, fixed type guide rods are expected to be used in the ABWR. Guide rods are the component for a shroud head and a steam dryer installation. However, guide rods are located near the main steam nozzle, therefore flow-induced vibration (FIV) is concern...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 725-732, April 14–18, 2002
Paper No: ICONE10-22344
... It is possible to simplify the reactor internal pump power supply system in the ABWR without affecting the core flow supply when a trip of all RIPs event occurs by eliminating the motor-generator sets and increasing the rotating inertia of the RIPs. This inertia increase due to an additional...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 301-307, April 14–18, 2002
Paper No: ICONE10-22489
... The purpose of this paper is to provide the quantitative evaluation method with regard to the Digital Protection systems (DPSs) that were newly adopted in the ABWR plants and to show the results of level1 PSA of the ABWR plants. 05 03 2009 ABWR level1 PSA DPS AM measures...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 439-446, April 25–29, 2004
Paper No: ICONE12-49321
... are studying the way of shortening construction period for the ABWR. In the previous study, we introduced a concept for shortening construction period and master schedule (M/S) based on the large-scale module method. In this study, we have developed the advanced concept for shortening construction...
Topics: Construction
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 105-109, April 25–29, 2004
Paper No: ICONE12-49235
... The first advanced boiling water reactor (ABWR)—Kashiwazaki-Kariwa Nuclear Power Station Unit 6 (K6)—was built in Japan by Tokyo Electric Power Corporation (TEPCO) in 1996. Subsequently, Kashiwazaki-Kariwa Nuclear Power Station Unit 7 (K7) was constructed (completed in 1997). The K6 and K7 have...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 403-409, April 25–29, 2004
Paper No: ICONE12-49118
... The reliability analysis of the digital reactor protection system (RPS) is one of the essential parts in the probabilistic safety assessment (PSA) of the advanced boiling water reactor (ABWR). In this study, the reliability model and methodology were modified to evaluate the reliability of the...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 121-125, April 25–29, 2004
Paper No: ICONE12-49333
... Kashiwazaki-Kariwa Nuclear Power Station Unit 6 and Unit 7 (K6 & K7) are the first advanced boiling water reactors (ABWR) in the world. Toshiba has been engaged in the design and construction of boiling water reactors (BWR) for Hamaoka Nuclear Power Station Unit 5 (H5) of Chubu Electric...