Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

approved: _____________________________________________________________________ Brian G. Woods The United States (US) Department of Energy (DOE) has identified the pebble-bed reactor as a high priority for US research with the end goal of licensing a pebble-bed reactor (PBR) for operation in the United States. Before this can be accomplished significant research must be done regarding the safety of the pebble-bed reactor. Of high interest is obtaining a better understanding of pebble-scale heat transfer and fluid flow within the PBR core. This thesis examines the ability of a hypothetical re-configured Oregon State University (OSU) High Temperature Test Facility (HTTF) to model the local phenomenon of the Chinese modular PBR (HTR-PM). Scaling analysis is used to quantify distortions that would occur between the HTR-PM and the scaled OSU HTTF. A one-fourth scaled test facility in height, core diameter, and pebble size is proposed. The scaling then demonstrates that this facility could model heat transfer, temperature profiles, and fluid forces found in the full scale HTR-PM with empirical correlations and non-dimensional ratios relating the HTR-PM and the scaled OSU HTTF. Computational fluid dynamics (CFD) are then used to produce computer simulations that show the scaling was satisfactorily performed. ©Copyright by Jordan Cox September 16, 2015 All Rights Reserved SCALING OF THE CHINESE HTR-PM REACTOR DESIGN FOR LICENSING AND TESTING AT THE OREGON STATE UNIVERSITY HIGH TEMPERATURE TEST FACILITY

[1]  Kwang-Yong Kim,et al.  Numerical treatment of pebble contact in the flow and heat transfer analysis of a pebble bed reactor core , 2007 .

[2]  S. Ergun Fluid flow through packed columns , 1952 .

[3]  Joshua J. Cogliati,et al.  PEBBLES: A COMPUTER CODE FOR MODELING PACKING, FLOW AND RECIRCULATIONOF PEBBLES IN A PEBBLE BED REACTOR , 2006 .

[4]  P. G. Rousseau,et al.  A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles , 2010 .

[5]  Eckart Laurien,et al.  Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes , 2012 .

[6]  Van der Meer,et al.  Modelling long–range radiation heat transfer in a pebble bed reactor , 2011 .

[7]  Chung-Yun Wu,et al.  Investigating the advantages and disadvantages of realistic approach and porous approach for closely packed pebbles in CFD simulation , 2010 .

[8]  E.H.K. Akaho,et al.  Analysis of fluid flow and heat transfer model for the pebble bed high temperature gas cooled reactor , 2012 .

[9]  E.M.J. Komen,et al.  Optimization of a pebble bed configuration for quasi-direct numerical simulation , 2012 .

[10]  Henri Fenech,et al.  Heat transfer and fluid flow in nuclear systems , 1981 .

[11]  Javier Ortensi,et al.  Improved Prediction of the Temperature Feedback in TRISO-Fueled Reactors , 2009 .

[12]  Charles P. Folsom,et al.  Effective thermal conductivity of tri-isotropic (TRISO) fuel compacts , 2012 .

[13]  Brian Jackson,et al.  Scaling analysis for the high temperature Gas Reactor Test Section (GRTS) , 2010 .

[14]  Glenn O. Brown,et al.  Henry Darcy and the making of a law , 2002 .

[15]  Fu Li,et al.  Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM , 2006 .

[16]  Yassin A. Hassan,et al.  Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 2: Accident and Thermal Fluids Analysis PIRTs , 2008 .

[17]  Danny Lathouwers,et al.  Testing a Nuclear Pebble-Bed Reactor Model in OpenFOAM , 2011 .

[18]  Wei Ji,et al.  A simplified DEM-CFD approach for pebble bed reactor simulations , 2012 .

[19]  E. Achenbach Heat and flow characteristics of packed beds , 1993 .

[20]  Su-Jong Yoon,et al.  Turbulence-induced Heat Transfer in PBMR Core Using LES and RANS , 2007 .

[21]  Janez Levec,et al.  Flow through packed bed reactors: 1. Single-phase flow , 2005 .

[22]  Abraham Christoffel Naudé Preller,et al.  Numerical modelling of flow through packed beds of uniform spheres , 2011 .

[23]  C. J. Visser Modelling Heat And Mass Flow Through Packed Pebble Beds: A Heterogeneous Volume-Averaged Approach , 2008 .

[24]  Benjamin L. Nelson Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility , 2009 .

[25]  Jae-Seung Roh,et al.  Thermal Emissivity of Nuclear Graphite as a Function of its Oxidation Degree (3): Structural Study using Scanning Electron Microscope and X-Ray Diffraction , 2011 .

[26]  B. E. Boyack,et al.  An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology , 1998 .

[27]  N. Tricot,et al.  Accident analysis for nuclear power plants with modular high temperature gas cooled reactors , 2008 .

[28]  Andrew C. Kadak,et al.  A future for nuclear energy: pebble bed reactors , 2005, Int. J. Crit. Infrastructures.

[29]  J. J. Janse van Rensburg,et al.  CFD applications in the Pebble Bed Modular Reactor Project: a decade of progress , 2011 .

[30]  H. E. Hoelscher,et al.  Effective thermal conductivity in packed beds , 1961 .

[31]  Wei Ji,et al.  A collective dynamics-based method for initial pebble packing in pebble flow simulations , 2012 .

[32]  Wei Ji,et al.  Pebble Flow and Coolant Flow Analysis Based on a Fully Coupled Multiphysics Model , 2013 .

[33]  H. Petersen,et al.  The properties of helium: Density, specific heats, viscosity, and thermal conductivity at pressures from 1 to 100 bar and from room temperature to about 1800 K , 1970 .

[34]  Timothy D. Burchell,et al.  Next Generation Nuclear Plant GAP Analysis Report , 2008 .

[35]  I. F. Macdonald,et al.  Flow through Porous Media-the Ergun Equation Revisited , 1979 .