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Showing 1 to 20 of 44 for “"boiling water reactor"”.
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A boiling water reactor simulator for stability analysis
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996.
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Optimization algorithms in boiling water reactor lattice design
Given the highly complex nature of neutronics and reactor physics, efficient methods of optimizing are necessary to effectively design the core reloading pattern and operate a nuclear reactor. The current popular methods for optimization are Simulated Annealing and the Genetic Algorithm; this paper …
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Chemical characterization of simulated boiling water reactor coolant
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990, and Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Chemical Engineering, 1990.
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Small Modular Boiling Water Reactor Combined with External Superheaters
… in this thesis is developing a Small Modular Boiling Water Reactor (SMBWR) combined with external superheaters. The SMBWR is a BWR-type small modular reactor. It is designed to adopt natural recirculation of coolant within its primary system. The SMBWR is also combined with the external …
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Conceptual design of an annular-fueled superheat boiling water reactor
… conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron moderation throughout the reactor core. A single fuel design is used in the core. …
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Stability analysis of the boiling water reactor : methods and advanced designs
… through a heated channel. In the development of boiling water reactors (BWRs), there has been considerable concern about the effects of such oscillations when coupled with neutronic feedback. The current trend of increasing reactor power density and relying more extensively on natural circulation …
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Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor
… the safety systems in the next generation boiling water reactor by analyzing the main steam line break loss of coolant accident performed in the Purdue university multi-dimensional test assembly (PUMA). RELAP5 code simulations, both for the PUMA main steam line break (MSLB) case and for the …
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A Semi-Analytical Method for the Thermal-Hydraulics of a Boiling Water Reactor
Made available in DSpace on 2017-07-06T18:59:14Z (GMT). No. of bitstreams: 3 Vandermyde_Mark_A_MS.pdf: 46312150 bytes, checksum: 094a60daa2636d18573e970c85add0ce (MD5) Vandermyde_Mark_A_MS_ABS.pdf: 451063 bytes, checksum: dac8cd25f58984ef8720768fc460b356 (MD5) license.txt: 4813 bytes, checksum: …
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TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly
… is a safety feature implemented in many Boiling Water Reactor (BWR) designs to re-flood a reactor during an accident. Significant experimental work has qualified the efficacy of spray cooling, and ongoing computational modeling efforts strive to more accurately portray the phenomena …
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A study of US nuclear power boiling water reactor, class IV, operating performance, 1992-1997
… to continue the improvement. A detailed study of Boiling Water Reactor, Class IV (BWR/4) performance over the past five years was conducted to gain insight to the nature of lost generation capability and develop a methodology to improve capability. Extensive electronic NRC records were used in …
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Evaluation of the economic simplified boiling water reactor human reliability analysis using the SHARP framework
… document for the Economic Simplified Boiling Water Reactor to have the new reactor design certified by the United States Nuclear Regulatory Commission. As part of the design process, the design control document was produced in 2006, and it includes a description of the human …
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Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research
This thesis discusses the development of Full scope BWR Simulator developed for human reliability course initiated at The Ohio State University. Human System Interface (HSI) guidelines followed to set-up the simulator room and steps undertaken to create the generic simulator from the plant based …
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The effect of thermal aging and boiling water reactor environment on Type 316L stainless steel welds
… at the 288°C operating temperature of a boiling water reactor (BWR) for example, where ductility reductions have been observed after several tens of thousands of hours. An experimental study has been completed in order to understand how the spinodal decomposition may affect material …
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Development of a fully implicit two-fluid, thermal-hydraulic model for boiling water reactor transient analysis
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980.
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Common Mode Failure Analysis of Test and Maintenance Procedures at LaSalle Unit #2 Boiling Water Reactor Plant 5/Mark II
Made available in DSpace on 2017-07-06T18:55:01Z (GMT). No. of bitstreams: 3 Lambright_John_A_MS.pdf: 89517257 bytes, checksum: c1942e50307929ab5ca2d521bf4d872a (MD5) Lambright_John_A_MS_ABS.pdf: 422087 bytes, checksum: f5dc75044a2cb7e320189bb1451f0c4f (MD5) license.txt: 4813 bytes, checksum: …
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Stability analysis of natural circulation in BWRs at high pressure conditions
At rated conditions, a natural circulation boiling water reactor (NCBWR) depends completely on buoyancy to remove heat from the reactor core. This raises the issue of potential unstable flow. oscillations. The objective of this work is to assess the characteristics of stability in a NCBWR at rated …
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Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
… were simulated in MELCOR using a generic boiling water reactor design that included Case I: Zircaloy-2 cladding, and Case II: FeCrAl cladding. The results from these two cases were analyzed using a one-way coupling approach with Thermochimica to demonstrate potential areas for the …
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Material Corrosion by Nuclear Reactor Coolants
… work investigated material corrosion by nuclear reactor coolants, including pressurized water reactor (PWR) coolant, boiling water reactor (BWR) coolant, high-temperature steam, lead-bismuth eutectic (LBE), and molten salt. Novel cladding materials for accident tolerant fuel (ATF) and additive …
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The consequence of station blackout in a nuclear power plant
… to achieve their function of cooling the reactor core and to safely shutdown the plant. The total loss of Alternating Current power supply to the essential and non-essential equipment of the plant is called Station Black Out. It is critical that the system that removes decay heat in the …
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