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151. A Global Review of PWR Nuclear Power Plants

153. CSPACE for a simulation of core damage progression during severe accidents

154. Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants

155. A developed analytical model for the pressurizer unit in nuclear power plants

156. Supplemental surveillance capsule application for the optimized power reactor, OPR1000, in Korea

157. Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term

158. Machine learning of LWR spent nuclear fuel assembly decay heat measurements

159. The detection and diagnosis model for small scale MSLB accident

160. Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core

161. Artificial neural network for predicting nuclear power plant dynamic behaviors

162. Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code

163. Development of a Robust Procedure for the Evaluation of Striation Spacings in Low Cycle Fatigue Specimens Tested in a Simulated PWR Environment

164. Math hydrogen catalytic recombiner: Engineering model for dynamic full-scale calculations.

165. METHODOLOGY FOR DETERMINATION OF ALARM AND WARNING SET-POINTS FOR RADIOACTIVE EFFLUENT MONITORS IN KOREAN PRESSURIZED WATER REACTORS.

166. Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics and structural analyses.

167. A symmetrical-nonuniform angular repartition strategy for the vane blades to improve the energy conversion ability of the coolant pump in the pressurized water reactor.

168. Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory.

169. New turbulence modeling for simulation of Direct Contact Condensation in two-phase pressurized thermal shock.

170. Exergy Analysis of a PWR Nuclear Steam Supply System – Part I, General theoretical model.

171. Exergy Analysis of a PWR Nuclear Steam Supply System - II part: a case study.

172. Customization of the coupled environment fracture model for predicting stress corrosion cracking in Alloy 600 in PWR environment.

173. Uniaxial low cycle fatigue behavior for pre-corroded 16MND5 bainitic steel in simulated pressurized water reactor environment.

174. Exergy and exergoeconomic analyses of a novel integration of a 1000 MW pressurized water reactor power plant and a gas turbine cycle through a superheater.

175. 压水堆燃料棒热力计算与(火用)分析.

176. On the characteristics of the flow and heat transfer in the core bypass region of a PWR.

177. Non linear Dynamic Inversion based controller design for load following operations in Pressurized Water Reactors with bounded Xenon oscillations.

178. 基于小波包和BP网络的松脱件质量估计.

179. Fatigue crack growth of 316NG austenitic stainless steel welds at 325 °C.

180. Application of metaheuristics to Loading Pattern Optimization problems based on the IAEA-3D and BIBLIS-2D data.

182. The Digital Acoustic Model of a Pressurized Water Reactor

183. Research and application of an in-service chemical decontamination process for high temperature and high pressure circuit

184. Evaluation of various large-scale energy storage technologies for flexible operation of existing pressurized water reactors

185. Investigation of Thermal Embrittlement of 17-4PH Stainless Steel Main Steam Isolation Valves

187. Verification and validation of isotope inventory prediction for back-end cycle management using two-step method

188. Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit.

189. Active disturbance rejection control of pressurized water reactor.

190. Predictive modeling of pressurized water reactor transients using nonlinear autoregressive with exogenous input neural network.

191. Simulation of IB-LOCA in TRACE : A semi-blind study of numerical simulations compared to the PKL test facility

192. Heat Transfer Enhancement in Subchannel Geometry of Pressurized Water Reactor Using Water-Based Yttrium Oxide Nanofluid

193. Baseline Examinations and Autoclave Tests of 65 and 100 dpa Flux Thimble Tube O-Ring Specimens

194. Oxidation Resistance and Stress Corrosion Cracking Susceptibility of 308L and 309L Stainless Steel Cladding Layers in Simulated Pressurized Water Reactor Primary Water

195. Analysis of a Radioactive Corrosion Material Collected from Control Rod Drive Mechanism Housing of a PWR Using an EPMA

196. Illustration of Nagra’s AMAC approach to Kori-1 NPP decommissioning based on experience from its detailed application to Swiss NPPs

197. An Experimental Study into the Hydrodynamics of the Loop Coolant Flows’ Mixing in the Nuclear Reactor Downcomer

198. Experimental investigation on ultrasonic surface rolling of Inconel 690TT

199. Design of Virtual SCADA Simulation System for Pressurized Water Reactor.

200. Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor

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