Download or read book Nuclear Data Uncertainty Quantification and Data Assimilation for a Lead cooled Fast Reactor written by and published by . This book was released on 2015 with total page 75 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Data Uncertainty Propagation for a Lead cooled Fast Reactor Combining TMC with Criticality Benchmarks for Improved Accuracy written by Erwin Alhassan and published by . This book was released on 2014 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Efficient Uncertainty Quantification for a Fast Spectrum Generation IV Reactor System written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This research is part of on-going research on the management of uncertainties in simulator predictions for Generation IV systems via optimum experimental design. The focus is on uncertainties originating due to input data. The objective is to devise an algorithmic framework for quantification of uncertainties, identification of their key sources, and ultimately guiding the design of validating experiments for their reduction. An integral part of this research is the development of uncertainty quantification algorithms for models involving many input data and output responses. This represents the focus of the research reported here. Uncertainty Quantification (UQ) in nuclear systems simulation is playing an increasing role in supporting decisions related to the research and development of advanced nuclear energy systems, especially those of interest to the Global Nuclear Energy Partnership (GNEP) and Next Generation Nuclear Plant (NGNP) programs. UQ will help assess the adequacy of existing simulation tools and associated databases, e.g. nuclear cross-section data, and provide guidance to areas of models and/or data where further development and/or measurements should be prioritized. A sensitivity and uncertainty analysis has been conducted to study the effects of neutron microscopic cross-section data uncertainty on macroscopic attributes that influence reactor core design, performance and safety for a Generation IV reactor concept. In the realm of reactor engineering, neutron cross-section data represents the basic physics of neutron interactions with matter and therefore have large impacts on evolution of flux, power, reactivity and other reactor performance attributes. Currently, we focus on uncertainties originating from cross-section data uncertainties, believed to be of primary significance for fast reactor calculations. This thesis presents a recent development of an UQ algorithm for increasing the efficiency of UQ to a level that enables its execution on a r.
Download or read book Sensitivity and Uncertainty Analysis of Nuclear Data for the Metallic Fueled ABR 1000 Sodium Cooled Fast Reactor written by Jun Shi and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The 1000 MWt Advanced Burner Reactor (ABR-1000) is a concept of Sodium-cooled Fast Reactor (SFR) developed at Argonne National Laboratory for the study of future reactor designs under the Global Nuclear Energy Partnership (GNEP) program. It was investigated within the OECD/NEA Working Party on Reactor Systems (WPRS) under the Sodium-cooled Fast Reactor core Feed-back and Transient response (SFR-FT) task force benchmark, which was completed in 2014. The results revealed that different nuclear data libraries contribute to the large discrepancies in some calculated neutronic parameters. This task force is followed up by another on-going OECD/NEA WPRS activity entitled as SFR Uncertainty Analysis in Modeling (SFR-UAM). In order to further investigate the properties of the ABR core, the impact of nuclear data uncertainties on the performance of a SFR is analyzed in detail in this master thesis using a "Best Estimate Plus Uncertainty" (BEPU) approach along with the nuclear data from the ENDF/B-VII.1 library. Several computer codes, including MC2-3, TWODANT, DIF3D, REBUS-3, PERSENT, DPT, and SAS4A/SASSYS-1, were used in this study. Significant uncertainties on neutronic parameters (e.g., sodium density coefficient, sodium void coefficient, structure density coefficient, Doppler coefficient) are found due to nuclear data, but thanks to the excellent reactor design, the margins to sodium boiling and fuel melting during the accidents are still large even if these non-negligible nuclear data uncertainties are considered.
Download or read book Nuclear Data for Innovative Fast Reactors written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: It is widely accepted that the current status of neutronics calculations for fast reactor design is such that present uncertainties on nuclear data should still be significantly reduced, in order to get full benefit from advances in modeling and simulation. Only a parallel effort in advanced simulation, in high accuracy validation experiments and in nuclear data improvement will provide designers with more general and well validated calculation tools to meet tight design target accuracies to further improve safety and economics. The present paper presents very recent results related to nuclear data uncertainty impact assessment, as a new step in the frame of an international activity, sponsored by OECD-NEA.
Download or read book Uncertainty Quantification and Propagation Methodology for Safety Analysis of Lead cooled Fast Reactors written by Ishita Trivedi and published by . This book was released on 2021 with total page 123 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Uncertainty Quantification and Propagation Methodology for Steady State Safety Analysis of Lead cooled Fast Reactors written by Ishita Trivedi and published by . This book was released on 2020 with total page 59 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Generation of Nuclear Data for Lead cooled Fast Reactors Using the Monte Carlo Method written by Carlos Garcia Domínguez and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The LEADER project goal is to improve and develop a scaled demonstrator of the LFR technology, ALFRED. The work in this thesis is focused in the ALFRED project framework and its mission is to obtain few-group cross section data for LFRs. Cross sections The neutron transport problem is crucial in nuclear engineering and nuclear reactor physics. Neutron transport theory and the diffusion theory applied to neutron reactions are briefly described, including their principles and hypothesis. The two different computational approaches to solve the neutron transport problem are summarized. The software used to obtain the data is based on a modification of the Monte Carlo method. Thus, some basic probability theory concepts are introduced. This section follows with the discussion of the Monte Carlo method and its principles, and how it can be applied to solve the neutron transport problem. Afterwards, the Serpent code is explained, as well as its features and characteristics. The process of creating a 2-dimension model of ALFRED fuel assembly and the elaboration of Serpent input files are detailed. Cross section data for five neutron energy groups and at different material temperatures is obtained by running several simulations using Serpent. The last section includes a brief description of LFR technology and some specific ALFRED features. Some advantages and disadvantages of LFRs are included, along with some proposals to solve the disadvantages. The last part of this section illustrates the proposed ALFRED core scheme, using the data publicly available to date.
Download or read book Systematic Sensitivity and Uncertainty Analysis of Sodium Cooled Fast Reactor Systems written by Friederike Bostelmann and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Mots-clés de l'auteur: sodium-cooled fast reactor ; uncertainty analysis ; sensitivity analysis ; nuclear data ; random sampling ; XSUSA ; SCALE.
Download or read book Improved Best Estimate Plus Uncertainty Methodology Including Advanced Validation Concepts to License Evolving Nuclear Reactors written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M & S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost saving purposes by showing further testing wold not enhance the quality of the validation of predictive tools. The proposed methodology is at a conceptual level. When matured and if considered favorably by the stakeholders, it could serve as a new framework for the next generation of the best estimate plus uncertainty licensing methodology that USNRC developed previously. In order to come to that level of maturity it is necessary to communicate the methodology to scientific, design and regulatory stakeholders for discussion and debates. This paper is the first step to establish this communication.
Download or read book Nuclear Constants No 8 written by USSR State Committee on the Utilization of Atomic Energy. International Atomic Energy Agency. Nuclear Data Section. International Nuclear Data Committee and published by . This book was released on 1972 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Constants No 8 written by USSR State Committee on the Utilization of Atomic Energy. International Atomic Energy Agency. Nuclear Data Section. International Nuclear Data Committee. USSR Nuclear Data Centre and published by . This book was released on 1974 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Sampling Based Nuclear Data Uncertainty Quantification for Continuous Energy Monte Carlo Codes written by and published by . This book was released on 2015 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Comparison of Uncertainty Quantification Methods for Fast Reactor Neutronics written by and published by . This book was released on 2010 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Scalable Methods for Uncertainty Quantification Data Assimilation and Target Accuracy Assessment for Multi Physics Advanced Simulation of Light Water Reactors written by Bassam Abdullah Ayed Khuwaileh and published by . This book was released on 2015 with total page 347 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis written by W. Wieselquist and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Compilation Evaluation and Production of Nuclear Data for Reactor Calculations written by Harry Alter and published by . This book was released on 1966 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
