1,625 results on '"Failure mode analysis"'
Search Results
102. Structural failure analysis of reactor vessels due to molten core debris
103. Failure of hierarchically structured materials: Statics and dynamics
104. Description of the grout system dynamic simulation
105. The United States Department of Energy (DOE) Computerized Accident/Incident Reporting System (CAIRS)
106. Methodology used in the integrated assessment of PIUS-600 safety
107. Auxiliary feedwater system aging study
108. Identification of important ``PIUS`` design considerations and accident sequences using qualitative plant assessment techniques
109. Seismically induced relay chatter risk analysis for the Advanced Test Reactor
110. Risk analysis of releases from accidents during mid-loop operation at Surry
111. Grain boundary chemistry effects on environment-induced crack growth of iron-based alloys
112. Performance demonstration requirements for eddy current steam generator tube inspection
113. Priority ranking of safety-related systems for structural enhancement assessment at Savannah River Site
114. Recent performance, lifetime, and failure modes of the 5045 klystron population at SLAC
115. Analysis of failed nuclear plant components
116. Detecting and mitigating aging in component cooling water systems
117. Life testing of a low voltage air circuit breaker
118. System response to relay chatter
119. A design for a high voltage magnet coil ringer test set
120. Reviewing the PIUS reactor design with failure modes effects and criticality analysis
121. Identification of important PIUS'' design considerations and accident sequences using qualitative plant assessment techniques
122. Improving safety through root cause analysis
123. BWR stability analysis at Brookhaven National Laboratory
124. Towards an analysis of leak-before-break assessments in the ductile tearing regime
125. Analysis of electronic component failures using high-density radiography
126. Designing magnetic systems for reliability
127. Mechanism of fatigue in micron-scale films of polycrystalline silicon for microelectromechanical applications
128. Development of deep drawn aluminum piston tanks
129. Research and development quality assurance planning
130. Some ongoing research in the U. S. that relates to nuclear reactor pressure components
131. MORT (Management Oversight and Risk Tree) based risk management
132. Evaluation of digital fault-tolerant architectures for nuclear power plant control systems
133. The use of light emission in failure analysis of CMOS ICs
134. Detection and mitigating rod drive control system degradation in Westinghouse PWRs
135. A failure probability estimate of Type 304 stainless steel piping
136. Metal-fueled HWR (heavy water reactors) severe accident issues: Differences and similarities to commercial LWRs (light water reactors)
137. Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors
138. Photovoltaic concentrator module reliability: Failure modes and qualification
139. Reduced-scope seimic analysis accomplished using probabilistic risk assessment techniques
140. Impact of support system failure limitations on probabilistic safety assessment and in regulatory decision making
141. Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment
142. Real-time LMR control parameter generation using advanced adaptive synthesis
143. Safety analysis for the Galileo Light-Weight Radioisotope Heater Unit
144. An analysis of the reliability of the Los Alamos National Laboratory electrical system
145. Assessment of thermal fatigue crack propagation in safety injection PWR lines
146. Applicability of base-isolation R D in non-reactor facilities to a nuclear reactor plant
147. Data banks for risk assessment at the Savannah River Site
148. A nonintrusive method for measuring the operating temperature of a solenoid-operated valve
149. An overview of the EBR-II PRA (Probabilistic Risk Assessment)
150. Recent developments in the CONTAIN-LMR code
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