Science and Technology of Nuclear Installations

Multiphysics Multiscale Coupling Modeling for Nuclear Reactor and Its Uncertainty Quantification


Publishing date
01 Jun 2020
Status
Closed
Submission deadline
31 Jan 2020

1University of Illinois Urbana-Champaign, Urbana Illinois, USA

2Karlsruhe Institute of Technology, Karlsruhe, Germany

3North Carolina State University, North Carolina, USA

4Tsinghua University, Beijing, China

This issue is now closed for submissions.
More articles will be published in the near future.

Multiphysics Multiscale Coupling Modeling for Nuclear Reactor and Its Uncertainty Quantification

This issue is now closed for submissions.
More articles will be published in the near future.

Description

The accurate prediction of nuclear reactor behavior using advanced numerical tools is an important issue for nuclear reactor design and safety analysis. The nuclear power plant is a complex nonlinear multiphysics, multiscale coupling system, as it requires consideration of the coupling among neutronics, thermal hydraulics, structural mechanics, chemical dynamics, and coupling between primary and secondary circuits. Moreover, there are a variety of uncertainty sources in each physical field and thus prediction involves the complicated propagation of uncertainty in the coupling system. Comprehensive, high-fidelity, multiphysics, multiscale coupling modeling with uncertainty quantification is a powerful numerical tool for the detailed analysis of both current and advanced reactor designs. However, the accurate prediction of nuclear reactor behavior still remains a challenging topic in the nuclear engineering community. Alongside advances in computational capability, there has been an exponentially growing interest in topics related to the advanced numerical methods and tools used in coupling modeling and its uncertainty quantification in order to pursue a realistic description of the physical behavior of nuclear power plants without conservative assumptions. Recently, emerging numerical methods and practical simulation tools significantly promote the development of related fields.

This special issue invites researchers from both academic and industrial backgrounds in nuclear reactors to share the latest and most significant achievements and promote recent developments in the area of nuclear reactor multiphysics coupling modeling and its uncertainty quantification. This includes the development of new nuclear reactor coupling methods, static and transient reactor behavior analyses using advanced coupling tools, new uncertainty methodology, and uncertainty analysis for the multiphysics modeling. Original research work, as well as critical review articles, is welcomed.

Potential topics include but are not limited to the following:

  • Nuclear reactor multiphysics multiscale coupling methodology developments
  • High fidelity computational methods for reactor coupling systems
  • Advanced coupling algorithm developments for nuclear reactors
  • Static and transient reactor behavior analyses using advanced coupling tools
  • Uncertainty methodology developments for nuclear reactors (statistical methods, Bayesian methods, hybrid methods, and inverse uncertainty methods)
  • Best-Estimate Plus Uncertainty (BEPU) for reactor physics, thermal-hydraulics, and fuel performance
  • BEPU methods and results for GEN-IV and other new designs
  • Challenges and recent trends for nuclear reactor multiphysics BEPU

Articles

  • Special Issue
  • - Volume 2020
  • - Article ID 8265146
  • - Research Article

A New Precursor Integral Method for Solving Space-Dependent Kinetic Equations in Neutronic and Thermal-Hydraulic Coupling System

Yingjie Wu | Baokun Liu | ... | Menglei Cui
  • Special Issue
  • - Volume 2020
  • - Article ID 8014521
  • - Research Article

Lognormal-Based Sampling for Fission Product Yields Uncertainty Propagation in Pebble-Bed HTGR

Yizhen Wang | Menglei Cui | ... | Fu Li
  • Special Issue
  • - Volume 2020
  • - Article ID 4765046
  • - Research Article

Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System

Dekui Zhan | Xinhai Zhao | ... | Huandong Chen
  • Special Issue
  • - Volume 2020
  • - Article ID 2562747
  • - Research Article

Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

Linrong Ye | Mingjun Wang | ... | G. H. Su
  • Special Issue
  • - Volume 2020
  • - Article ID 5090597
  • - Research Article

Transient Study on the HTR-PM with TINTE-vPower Coupling Code Package

Jun Sun | Ximing Sun | Yanhua Zheng
  • Special Issue
  • - Volume 2020
  • - Article ID 3961095
  • - Research Article

Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors

Ishita Trivedi | Jason Hou | ... | Fausto Franceschini
  • Special Issue
  • - Volume 2020
  • - Article ID 6798738
  • - Research Article

Numerical Simulation and Validation for Early Core Degradation Phase under Severe Accidents

Dekui Zhan | Xinhai Zhao | ... | Huandong Chen
  • Special Issue
  • - Volume 2020
  • - Article ID 7526864
  • - Research Article

Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis

Jason Hou | Maria Avramova | Kostadin Ivanov
  • Special Issue
  • - Volume 2020
  • - Article ID 2764634
  • - Research Article

Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations

Dean Price | Majdi I. Radaideh | ... | Tomasz Kozlowski
  • Special Issue
  • - Volume 2020
  • - Article ID 9235783
  • - Research Article

Sensitivity and Uncertainty Analysis of the Maximum Fuel Temperature under Accident Condition of HTR-PM

Chen Hao | Peijun Li | ... | Rongrui Yang
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate32%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore1.700
Impact Factor0.825
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