nuclear reactor - Globe Thesis

Keyword [nuclear reactor] Result: 101 - 120 \| Page: 6 of 8
101.	The near boiling reactor: Conceptual design of a small inherently safe nuclear reactor to extend the operational capability of the Victoria Class submarine
102.	Thermal-hydraulic modeling of the Pennsylvania State University Breazeale Nuclear Reactor (PSBR)
103.	Transient behavior of a nuclear reactor coupled to an accelerator
104.	Development of a piezoelectric ultrasonic array sensor for nuclear reactor applications
105.	Nonlinear Ultrasonic Measurements in Nuclear Reactor Environments
106.	The Super Near Boiling Reactor The 25MW Super Near Boiling Nuclear Reactor (SNB25) in Transient States and Confirmation of its Inherent Safety
107.	Thermal and hydrothermal stability of selected polymers in a nuclear reactor environment
108.	An advanced nuclear reactor analysis methodology for heterogeneous cores
109.	Multiscale Methods for Nuclear Reactor Analysis
110.	Investigation of Thermal Hydraulics of a Nuclear Reactor Moderator
111.	Parametric study of a vortex diode for a nuclear reactor emergency shut-off system
112.	Turbulent steam jets in enclosed structures: An application to nuclear reactor accident analysis
113.	Transient two-phase flow and application to severe nuclear reactor accident
114.	Model-based control of a research nuclear reactor
115.	Optical fibers in nuclear reactor radiation environments
116.	A Monte Carlo program to calculate the exposure rate from airborne radioactive gases inside a nuclear reactor containment building
117.	SOME IMPLICIT AND EXPLICIT TIME DISCRETIZATION SCHEMES FOR STIFF SYSTEMS (NUCLEAR REACTOR KINETICS, HEAT TRANSFER)
118.	A THEORETICAL STUDY OF ENERGETIC INTERACTIONS BETWEEN HIGH TEMPERATURE MOLTEN MATERIALS AND A LOW TEMPERATURE FLUID (FUEL-COOLANT, INTERACTION, VAPOR EXPLOSION, HEAVY WATER NUCLEAR REACTOR)
119.	APPLICATION OF IMPORTANCE MEASURES TO NUCLEAR REACTOR SYSTEMS AND THE DEVELOPMENT OF SYSTEMS PERFORMANCE STANDARDS BASED ON PROBABILISTIC RISK ASSESSMENTS
120.	OPTIMAL THORIUM-FUELED CANDU NUCLEAR REACTOR FUEL MANAGEMENT
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