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Towards a Probabilistic Analysis of Pressurized Thermal Shock

Volume 3: Fluid-Structure Interaction; High Pressure Technology, 2022
Abstract Pressurized thermal shock (PTS) in a reactor pressure vessel could lead to a sudden brittle and catastrophic cleavage fracture. The combination of radiation embrittlement, the thermal stresses, and low temperatures can cause severe conditions for the structures.
C. D. Versteylen   +5 more
openaire   +1 more source

Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel

Journal of Pressure Vessel Technology, 2014
Both deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs). The FAVOR code is applied to calculate the probabilities for crack initiation and failure of the RPV subjected to two transients, by considering crack distributions based on cracks observed in ...
Qian, Guian, Niffenegger, Markus
openaire   +3 more sources

Consequence evaluation for pressurized thermal shock

Nuclear Engineering and Design, 1985
Abstract In order to estimate the risk associated with Pressurized Thermal Shock (PTS), a sample calculation of the core melt frequency and offsite consequences has been performed for Oconee Unit 1, a Babcock and Wilcox pressurized water reactor located in the United States.
Richard J. Barrett, Edward D. Throm
openaire   +1 more source

Uncertainties in Pressurized Thermal Shock Analyses

Volume 3: Design and Analysis, 2019
Abstract Integrity assessment of reactor pressure vessels (RPVs) can be performed either by deterministic fracture mechanics (DFM) or/and by probabilistic fracture mechanics (PFM) analyses. In European countries and Switzerland, only DFM analyses are required.
Niffenegger, M.   +7 more
openaire   +2 more sources

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, 2021
Abstract One of the most important issues for the assessment of life time extension of a nuclear power plant is whether the Reactor Pressure Vessel (RPV) can maintain structural integrity under Pressurized Thermal Shock (PTS) phenomenon.
openaire   +1 more source

Influence of thermal shock of piezoelectric pressure sensors on the measurement of explosion pressures

Journal of Loss Prevention in the Process Industries, 2021
Abstract Piezoelectric pressure sensors are susceptible to changing temperatures, because resulting mechanical deformations of the sensor membrane and housing may exert a positive or negative force on the piezo crystal, thus changing the reading of this sensor.
Tim Krause   +2 more
openaire   +1 more source

Pressurized Thermal Shock — An Integrated Analysis

1984
The potential for long term neutron embrittlement of reactor vessels has been recognized for a number of years. Reactor vessel thermal shock is not a new concern, but with a growing number of plants approaching their mid-lives, it is a concern that must be understood and dealt with.
B. Chexal   +4 more
openaire   +1 more source

Quantification of Thermal Shock in a Piezoelectric Pressure Transducer

SAE Technical Paper Series, 2005
<div class="htmlview paragraph">One of the major problems limiting the accuracy of piezoelectric transducers for cylinder pressure measurements in an internal-combustion (IC) engine is the thermal shock. Thermal shock is generated from the temperature variation during the cycle.
Seokhwan Lee   +5 more
openaire   +1 more source

Large thermal gradients on structural integrity of a reactor pressure vessel subjected to pressurized thermal shocks

International Journal of Pressure Vessels and Piping, 2020
Abstract Pressurized-thermal-shocks (PTSs) are the most severe accidents that impact the structural integrity of a pressurized water reactor pressure vessel (RPV). In general, the one-dimensional thermal-hydraulic analysis results for PTS transients were often used as the loading conditions for structural integrity evaluation of RPV, but may cause ...
Pin-Chiun Huang   +3 more
openaire   +1 more source

Thermal shock experiments on the HDR pressure vessel

Nuclear Engineering and Design, 1991
Abstract Within the HDR-Safety Program cracks in the HDR pressure vessel were generated and propagated by cyclic and monotonic thermal shock loadings. After various test stages the damaged zones of the RPV were removed and examined both fractographically and metallographically. These post-test examinations showed, that during the cyclic thermal shock
U. Eisele   +3 more
openaire   +1 more source

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