scholarly journals The Best Estimate Plus Uncertainty Challenge in the Current Licensing Process of Present Reactors

2011 ◽  
Vol 2011 ◽  
pp. 1-9 ◽  
Author(s):  
Francesco D'Auria ◽  
Oscar Mazzantini
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Computational Tools ◽  
Best Estimate ◽  
Safety Margins ◽  
Heavy Water Reactor ◽  
Key Steps ◽  
Uncertainty Method ◽  
Selection Of

Within the licensing process of the KWU Atucha II PHWR (Pressurized Heavy Water Reactor), the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key steps of the entire process are basically two: (a) the selection of PIE (Postulated Initiating Events) and (b) the analysis by best estimate models supported by uncertainty evaluation. Otherwise, key elements of the approach are (1) availability of qualified computational tools including suitable uncertainty method, (2) demonstration of quality, and (3) acceptability and endorsement by the licensing authority. The effort of issuing Chapter 15 is terminated at the time of issuing of the present paper, and the safety margins available for the operation of the concerned NPP (Nuclear Power Plant) have been quantified.

The Best-Estimate Plus Uncertainty (BEPU) Challenge in the Licensing of Current Generation of Reactors

2011 ◽  
Author(s):  
A. Petruzzi ◽  
N. Muellner ◽  
F. D’Auria ◽  
O. Mazzantini
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Current Generation ◽  
Computational Tools ◽  
Best Estimate ◽  
Safety Margins ◽  
Heavy Water Reactor ◽  
Key Steps ◽  
Uncertainty Method ◽  
Selection Of

Within the licensing process of the Atucha II PHWR (Pressurized Heavy Water Reactor) the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key steps of the entire process are basically two: a) the selection of PIE (Postulated Initiating Events) and, b) the analysis by best estimate models supported by uncertainty evaluation. Otherwise, key elements of the approach are: 1) availability of qualified computational tools including suitable uncertainty method; 2) demonstration of quality; 3) acceptability and endorsement by the licensing authority. The effort of issuing Chapter 15 is terminated at the time of issuing of the present paper and the safety margins available for the operation of the concerned NPP (Nuclear Power Plant) have been quantified.

The BEPU Challenge in Current Licensing of Nuclear Reactors

2010 ◽  
Author(s):  
F. D’Auria ◽  
A. Petruzzi ◽  
N. Muellner ◽  
O. Mazzantini
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactors ◽  
Computational Tools ◽  
Best Estimate ◽  
Safety Margins ◽  
Heavy Water Reactor ◽  
Key Steps ◽  
Uncertainty Method ◽  
Selection Of

Within the licensing process of the Atucha II PHWR (Pressurized Heavy Water Reactor) the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key steps of the entire process are basically two: a) the selection of PIE (Postulated Initiating Events) and, b) the analysis by best estimate models supported by uncertainty evaluation. The key elements of the approach are: 1) availability of qualified computational tools including suitable uncertainty method; 2) demonstration of quality; 3) acceptability and endorsement by the licensing authority. The effort of issuing Chapter 15 is terminated at the time of issuing of the present paper and the safety margins available for the operation of the concerned NPP (Nuclear Power Plant) have been quantified.

Qualification and Uncertainty Evaluation of a Best Estimate Loca Study of the Mochovce NPP by RELAP5/3.2-Gamma and CIAU

2006 ◽  
Author(s):  
Boris Kvizda ◽  
Alessandro Petruzzi ◽  
Francesco S. D’Auria
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Uncertainty Evaluation ◽  
Internal Assessment ◽  
Best Estimate ◽  
Uncertainty Calculation ◽  
Project Objectives ◽  
Uncertainty Method

The paper describes the work that has been done in cooperation between VUJE, Inc. (Slovakia) and University of Pisa (UNIPI, Italy). The aim was to evaluate Best Estimate Plus Uncertainty calculation (BEPU) of Mochovce Nuclear Power Plant WWER-440/213 (NPP) for the selected LOCA scenario utilizing the Code with the capability of Internal Assessment of Uncertainty (CIAU) developed at UNIPI. At the basis of CIAU, there is the Uncertainty Method based on Accuracy Extrapolation (UMAE) previously proposed by UNIPI. The project was considered as a full pilot BEPU application for WWER-440 type of unit in VUJE, Inc. that can be taken as a basis for utilization in licensing process later on. Project objectives are as follows: • To prove capability of available Mochovce NPP nodalization for RELAP5/3.2.2 gama to predict meaningful results for LOCA type accidents following UMAE procedure [1]. • To apply the CIAU [2, 3] to a LOCA transient selected for the Mochovce NPP and produce uncertainty bands for selected relevant parameters.

New Trends in Accurate Simulations for the Verification of Safety Margins in the Nuclear Power Plant Industry: Application of Virtual Performance Solution™ for the Response of Immersed Structures Subjected to Earthquakes

2011 ◽  
Author(s):  
Alain Tramec¸on ◽  
Jorg Kuhnert ◽  
Laurent Mouchette ◽  
Morgane Perrin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Dynamic Simulations ◽  
Finite Point ◽  
Fluid Structure ◽  
Finite Element Software ◽  
Mesh Free ◽  
Safety Margins ◽  
Non Linear

Constraints on the safety of nuclear power plant components have increased recently along with the necessity to extend the lifespan of existing plants. For example, the acceleration levels to be sustained by the plant equipment during an earthquake have been increased many folds by the safety regulation agencies. Industrial and economic requirements plead for a verification of unknown safety margins, by accurate and physics based models taking into account all non-linear effects (for example contacts and fluid structure interaction). These effects are only approximately represented by standard linear analysis tools. Virtual Performance Solution (VPS), developed by ESI Group, includes (among other capabilities) a structural finite element software for non-linear, high velocity, dynamic simulations (PAM-CRASH), as well as a coupled, mesh free CFD module, FPM (Finite Point Method), developed in partnership with Fraunhofer ITWM. This solution accurately predicts fluid structure interactions, taking into account non-linear structural effects (contacts, friction, damping…) as well as complex fluid influences.

Site Selection of a Dual Purpose Nuclear Power Plant in Saudi Arabia

1987 ◽  
Vol 79 (3) ◽  
pp. 311-321 ◽  
Author(s):  
Fahmy M. Hussein ◽  
Mohamed A. Obeid ◽  
Khalid S. El-Malahy
Keyword(s):  
Saudi Arabia ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Site Selection ◽  
Nuclear Power ◽  
Dual Purpose ◽  
Selection Of

Terrestrial Distribution of 14C in the Vicinity of Qinshan Nuclear Power Plant, China

Radiocarbon ◽  
2013 ◽  
Vol 55 (1) ◽  
pp. 59-66 ◽  
Author(s):  
Zhongtang Wang ◽  
Yuanyi Xiang ◽  
Qiuju Guo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Specific Activity ◽  
Background Level ◽  
Food Samples ◽  
Pine Needles ◽  
Activity Levels ◽  
Heavy Water Reactor ◽  
Rice Samples

We used accelerator mass spectrometry (AMS) to study radiocarbon-specific activity levels in agricultural and botanical samples (moss and pine needles) distributed within a 6.5-km radius of the Qinshan Nuclear Power Plant (NPP). The 14C-specific activity in moss samples (ranging from 265.6 to 223.0 Bq/kg C) decreased with increased distance from the stacks of Plant III (heavy water reactor) and reached the background level (223.8 Bq/kg C) at 6.5 km distance. Compared to the pine needles, the moss was a better indicator for investigating the 14C distribution near Qinshan NPP. The 14C-specific activity distribution in moss samples showed that the diffusion of 14C discharged from the Qinshan NPP was affected by both geographical and meteorological factors. Excess 14C-specific activity in the food samples ranged from 8.5 to 13.0 Bq/kg C (except for rice samples), resulting in a minimal radiation dose of 0.5 μSv per year to the public.

Decoupling Criteria for Multi-Connected Equipment

1998 ◽  
Vol 120 (1) ◽  
pp. 93-98 ◽  
Author(s):  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
S. C. Mahajan ◽  
K. Suzuki
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Internal Structure ◽  
Heavy Water ◽  
Nuclear Power ◽  
Seismic Analysis ◽  
Real Life ◽  
Water Reactor ◽  
Reactor Building ◽  
Heavy Water Reactor

Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water reactor building internal structure and steam generator.

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