scholarly journals Probabilistic evaluation of concrete strains for assessing prestressing loss in nuclear containment segments

2016 ◽  
Author(s):  
Georgios Balomenos ◽  
Mahesh Pandey
Keyword(s):  
Nuclear Containment ◽  
Probabilistic Evaluation ◽  
Prestressing Loss

Probabilistic finite element investigation of prestressing loss in nuclear containment wall segments

2017 ◽  
Vol 311 ◽  
pp. 50-59 ◽  
Author(s):  
Georgios P. Balomenos ◽  
Mahesh D. Pandey
Keyword(s):  
Finite Element ◽  
Nuclear Containment ◽  
Prestressing Loss

Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions

2021 ◽  
pp. 108862
Author(s):  
Zhongcheng Li ◽  
Junying Guo ◽  
Song Jin ◽  
Peng Zhang ◽  
Jinxin Gong
Keyword(s):  
Safety Evaluation ◽  
Fragility Analysis ◽  
Nuclear Containment ◽  
Prestressing Loss ◽  
Probabilistic Safety

Behavior of Reinforced Concrete Nuclear Containment Structures Subjected to Tri-Directional Shear Stresses

2012 ◽  
Author(s):  
Moheb Labib ◽  
Yashar Moslehy ◽  
Ashraf Ayoub
Keyword(s):  
Reinforced Concrete ◽  
Shear Stresses ◽  
Nuclear Containment

scholarly journals Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

2012 ◽  
Vol 2012 ◽  
pp. 1-7 ◽  
Author(s):  
Pavan K. Sharma ◽  
B. Gera ◽  
R. K. Singh ◽  
K. K. Vaze
Keyword(s):  
Nuclear Power ◽  
Nuclear Reactor ◽  
Pressure Rise ◽  
Dynamics Modeling ◽  
Steam Condensation ◽  
Noncondensable Gases ◽  
Nuclear Containment ◽  
Design Basis ◽  
Lumped Parameter ◽  
Transport Calculation

In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA) or beyond design basis accidents (BDBA). For accurate calculation of the temperature/pressure rise and hydrogen transport calculation in nuclear reactor containment due to such scenarios, wall condensation heat transfer coefficient (HTC) is used. In the present work, the adaptation of a commercial CFD code with the implementation of models for steam condensation on wall surfaces in presence of noncondensable gases is explained. Steam condensation has been modeled using the empirical average HTC, which was originally developed to be used for “lumped-parameter” (volume-averaged) modeling of steam condensation in the presence of noncondensable gases. The present paper suggests a generalized HTC based on curve fitting of most of the reported semiempirical condensation models, which are valid for specific wall conditions. The present methodology has been validated against limited reported experimental data from the COPAIN experimental facility. This is the first step towards the CFD-based generalized analysis procedure for condensation modeling applicable for containment wall surfaces that is being evolved further for specific wall surfaces within the multicompartment containment atmosphere.

scholarly journals Review of Practice for Deeply Embedded/Buried NPP Structures Subject to Seismic Loadings

2004 ◽  
Author(s):  
J. Xu ◽  
C. Miller ◽  
C. Hofmayer ◽  
H. Graves
Keyword(s):  
National Laboratory ◽  
Earth Pressure ◽  
Nuclear Regulatory Commission ◽  
Brookhaven National Laboratory ◽  
Nuclear Containment ◽  
The Us ◽  
Reactor Building ◽  
Seismic Loadings ◽  
Knowledge And Practice ◽  
Regulatory Commission

Motivated by many design considerations, several conceptual designs for advanced reactors have proposed that the entire reactor building and a significant portion of the steam generator building will be either partially or completely embedded below grade. For the analysis of seismic events, the soil-structure interaction (SSI) effect and passive earth pressure for these types of deeply embedded structures will have a significant influence on the predicted seismic response. Sponsored by the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) is carrying out a research program to assess the significance of these proposed design features for advanced reactors, and to evaluate the existing analytical methods to determine their applicability and adequacy in capturing the seismic behavior of the proposed designs. This paper summarizes a literature review performed by BNL to determine the state of knowledge and practice for seismic analyses of deeply embedded and/or buried (DEB) nuclear containment type structures. Included in the paper is BNL’s review of the open literature of existing standards, tests, and practices that have been used in the design and analysis of DEB structures. The paper also provides BNL’s evaluation of available codes and guidelines with respect to seismic design practice of DEB structures. Based on BNL’s review, a discussion is provided to highlight the applicability of the existing technologies for seismic analyses of DEB structures and to identify gaps that may exist in knowledge and potential issues that may require better understanding and further research.

Probabilistic Evaluation of Global Technically Recoverable Tight Gas Resources

2015 ◽  
Vol 7 (03) ◽  
pp. 112-119
Author(s):  
Zhenzhen Dong ◽  
Stephen A. Holditch ◽  
Walter B. Ayers
Keyword(s):  
Tight Gas ◽  
Probabilistic Evaluation
Sign in / Sign up

Export Citation Format

Share Document