scholarly journals EVALUATION OF THE ESFR END OF CYCLE STATE AND DETAILED ANALYSIS OF SPATIAL DISTRIBUTIONS OF REACTIVITY COEFFICIENTS

2021 ◽  
Vol 247 ◽  
pp. 02001
Author(s):  
Una Davies ◽  
Marat Margulis ◽  
Eugene Shwageraus ◽  
Emil Fridman ◽  
Nuria Garcia-Herranz ◽  
...  
Keyword(s):  
Detailed Analysis ◽  
Spatial Distributions ◽  
Reactor Physics ◽  
Physics Simulation ◽  
Reactivity Coefficients ◽  
High Degree ◽  
Commercial Size ◽  
Simulation Codes

The ESFR-SMART project is the latest iteration of research into the behaviour of a commercial-size SFR core throughout its lifetime. As part of this project the ESFR core has been modelled by a range of different reactor physics simulation codes at its end of cycle state, and the important safety relevant parameters evaluated. These parameters are found to agree well between the different codes, giving good confidence in the results. A detailed mapping of the local sodium void worth is also performed due to the problems associated with the positive void coefficient seen in large SFR designs. The local void worth maps show that the use of zone-wise coefficients replicates the important reactivity feedbacks to a high degree, indicating their suitability for use in SFR simulations.

Evaluation of the Esfr End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

2021 ◽  
Author(s):  
Una Baker ◽  
Marat Margulis ◽  
Eugene Shwageraus ◽  
Emil Fridman ◽  
Antonio Jiménez-Carrascosa ◽  
...  
Keyword(s):  
Uncertainty Analysis ◽  
Operating Conditions ◽  
Reactor Physics ◽  
Horizon 2020 ◽  
Decay Heat ◽  
Continuous Energy ◽  
Reactivity Coefficients ◽  
Sensitivity And Uncertainty Analysis ◽  
Commercial Size ◽  
Good Agreement

Abstract The Horizon 2020 ESFR-SMART project investigates the behaviour of the commercial-size European Sodium-cooled Fast Reactor (ESFR) throughout its lifetime. This paper reports work focused on the End of Equilibrium Cycle (EOEC) loading of the ESFR, including neutronic analysis, core- and zone-wise reactivity coefficients, and more detailed local mapping of important safety-relevant parameters. Sensitivity and uncertainty analysis on these parameters have also been performed and a detailed investigation into decay heat mapping carried out. Due to the scope of this work the results have been split into three papers. The nominal operating conditions and both zone-wise and local mapping of reactivity coefficients are considered in this paper; the sensitivity and uncertainty analysis are detailed in Margulis et al. [1]; and the decay heat mapping calculations are reported in Jimenez-Carrascosa et al. [2]. The work was performed across four institutions using both continuous-energy Monte Carlo and deterministic reactor physics codes. A good agreement is observed between the methods, verifying the suitability of these codes for simulation of large, complicated reactor configurations; and giving confidence in the results for the most limiting ESFR EOEC core state for safety analysis. The results from this work will serve as basis for the transient calculations planned for the next stage of work on the ESFR, allowing for more in-depth studies to be performed on the multiphysics behaviour of the reactor.

scholarly journals Enhanced verification test suite for physics simulation codes

2008 ◽  
Author(s):  
James R. Kamm ◽  
Jerry S. Brock ◽  
Scott T. Brandon ◽  
David L. Cotrell ◽  
Bryan Johnson ◽  
...  
Keyword(s):  
Test Suite ◽  
Physics Simulation ◽  
Verification Test ◽  
Simulation Codes

scholarly journals UNCERTAINTY ANALYSIS TO C5G7-TD BENCHMARK BASED ON THE COST METHOD

2021 ◽  
Vol 247 ◽  
pp. 15007
Author(s):  
Liangzhi Cao ◽  
Zhuojie Sui ◽  
Bo Wang ◽  
Chenghui Wan ◽  
Zhouyu Liu
Keyword(s):  
Uncertainty Analysis ◽  
Nuclear Reactor ◽  
Uncertainty Propagation ◽  
Nuclear Data ◽  
Reactor Physics ◽  
Oriented Sample ◽  
Neutron Kinetics ◽  
Minimal Sample ◽  
Physics Simulation ◽  
The Cost

A method of Covariance-Oriented Sample Transformation (COST) has been proposed in our previous work to provide the converged uncertainty analysis results with a minimal sample size. The transient calculation of nuclear reactor is a key part of the reactor-physics simulation, so the accuracy and confidence of the neutron kinetics results have attracted much attention. In this paper, the Uncertainty Quantification (UQ) function of the high fidelity neutronics code NECP-X has been developed based on our home-developed uncertainty analysis code UNICORN, building a platform for the UQ of the transient calculation. Furthermore, the well-known space-time heterogeneous neutron kinetics benchmark C5G7 and its uncertainty propagation from the nuclear data to the interested key parameters of the core have been investigated. To address the problem of “the curse of dimensionality” caused by the large number of input parameters, the COST method has been applied to generate multivariate normal-distribution samples in uncertainty analysis. As a result, the law of the assembly/pin normalized power and their uncertainty with respect to time after introducing an instantaneous perturbation has been obtained. From the numerical results, it can be observed that the maximum relative uncertainties for the assembly normalized power can up to be about 1.65% and the value for the pin-wise power distributions can be about 2.71%.

scholarly journals CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

Energies ◽  
2021 ◽  
Vol 14 (5) ◽  
pp. 1220
Author(s):  
Sebastian Davies ◽  
Ulrich Rohde ◽  
Dzianis Litskevich ◽  
Bruno Merk ◽  
Paul Bryce ◽  
...  
Keyword(s):  
Software Development ◽  
Turbulent Mixing ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Journal Article ◽  
Thermal Hydraulics ◽  
Reactor Physics ◽  
Wide Range ◽  
The Uk ◽  
Simulation Codes

Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power. Full-core coupled reactor physics at the rod level are not provided by most simulation codes. This has led in the UK to the development of a multiscale and multiphysics software development focused on LWRS. In terms of the thermal hydraulics, simulation codes suitable for this multiscale and multiphysics software development include the subchannel code CTF and the thermal hydraulics module FLOCAL of the nodal code DYN3D. In this journal article, CTF and FLOCAL thermal hydraulics validations and verifications within the multiscale and multiphysics software development have been performed to evaluate the accuracy and methodology available to obtain thermal hydraulics at the rod level in both simulation codes. These validations and verifications have proved that CTF is a highly accurate subchannel code for thermal hydraulics. In addition, these verifications have proved that CTF provides a wide range of crossflow and turbulent mixing methods, while FLOCAL in general provides the simplified no-crossflow method as the rest of the methods were only tested during its implementation into DYN3D.

Current status of fast reactor physics reactivity coefficients

1985 ◽  
Vol 16 (3) ◽  
pp. 231-250 ◽  
Author(s):  
Leo G. Lesage ◽  
Michael J. Lineberry ◽  
Harold F. McFarlane
Keyword(s):  
Fast Reactor ◽  
Current Status ◽  
Reactor Physics ◽  
Reactivity Coefficients

Kant im Kino

2015 ◽  
Vol 63 (1) ◽  
Author(s):  
Jihae Chung
Keyword(s):  
Detailed Analysis ◽  
Textual Analysis ◽  
Sensory Experience ◽  
Philosophical Investigation ◽  
Basic Assumptions ◽  
The Sublime ◽  
Film Reception ◽  
Mental Perception ◽  
High Degree

AbstractUsing a detailed analysis of scenes from Into the Wild (2007), this study aims to demonstrate how the theory of the sublime, particularly Kant’s theory, can be applied to film. To this purpose, the sublime will be referred to in the film heuristically as the Cinematic Sublime. My basic assumptions here are as follows: First, Kant’s theory of the sublime can be seen as a philosophical and aesthetic emotion-oriented teaching. Second, the emotional-sensory experience of the sublime is always manifested in the interconnection of both the film’s technical apparatus as well as its physical and mental perception. So the different modes of experiencing of the Cinematic Sublime can be described as filmic emotions. As a consequence, the phenomenon of the Cinematic Sublime is a textually constructed sensation, which can be analyzed with the help of textual analysis. Third, the Cinematical Sublime can be experienced through intersubjective activities of the audience during film reception, requiring a high degree of imagination, empathy and constitutive perception. Thus, I am undertaking a film-philosophical investigation that can be described as an analysis of film emotions based upon the textuality of film

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