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Advanced High Temperature Reactor Thermal Hydraulics Analysis and Salt Clean-Up System Description

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Advanced High Temperature Reactor Thermal Hydraulics Analysis and Salt Clean-Up System Description ORNL/TM-2014/499 Advanced High Temperature Reactor Thermal Hydraulics Analysis and Salt Clean-up System Description Compiled by G. L. Yoder Approved for public release: Contributors distribution is unlimited. A. T. Bopp D. E. Holcomb W. D. Pointer D. Wang September 2014 DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Website http://www.ntis.gov/help/ordermethods.aspx Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Website http://www.osti.gov/contact.html This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. ORNL/TM-2014/499 Reactor and Nuclear Systems Division Advanced High Temperature Reactor Thermal Hydraulics Analysis and Salt Clean-up System Description Complied by G. L. Yoder Contributors A. T. Bopp D. E. Holcomb W. D. Pointer D. Wang Date Published: September 2014: Prepared by OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-6283 managed by UT-BATTELLE, LLC for the US DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725 CONTENTS Page LIST OF FIGURES ..................................................................................................................................... vi LIST OF TABLES ....................................................................................................................................... ix LIST OF ACRONYMS ............................................................................................................................... xi NOMENCLATURE ................................................................................................................................... xii 1. INTRODUCTION .................................................................................................................................. 1 2. FUEL ASSEMBLY COMPUTATIONAL FLUID DYNAMICS ANALYSIS ..................................... 4 2.1 CORE AND FUEL ASSEMBLY DESIGN FEATURES .............................................................. 4 2.2 FUEL ASSEMBLY CHARACTERIZATION .............................................................................. 7 2.2.1 Material Properties .............................................................................................................. 7 2.2.2 Coolant Channel Thermal Hydraulic Characteristics ......................................................... 9 2.2.3 Natural versus Forced Convection ...................................................................................... 9 2.2.4 Power Profile .................................................................................................................... 10 2.3 CFD Simulation Methodology ..................................................................................................... 10 2.4 MESH GENERATION AND MESH SENSITIVITY STUDIES ................................................ 11 2.5 SIMULATION RESULTS ........................................................................................................... 14 2.5.1 Baseline Reference Model ................................................................................................ 14 2.5.2 Conductivity Sensitivity Studies ....................................................................................... 17 2.5.3. Initial Full Assembly Flow Studies ................................................................................... 20 2.6 FUEL ASSEMBLY DESIGN RECOMMENDATIONS AND FUTURE WORK ..................... 22 3. AHTR THERMAL HYDRAULIC SYSTEM ANALYSIS ................................................................. 23 3.1 TRACE MODELING AND SIMULATION OF AHTR ............................................................. 23 3.1.1. Overall Plant Features ...................................................................................................... 23 3.1.2. TRACE Model Description .............................................................................................. 23 3.1.3 Simulations ....................................................................................................................... 39 3.1.4 Summary of TRACE Model Development ....................................................................... 44 4. FHR PRIMARY COOLANT CLEANING OVERVIEW ................................................................... 46 4.1 PERFORMANCE REQUIREMENTS......................................................................................... 46 4.2 POTENTIAL CONTAMINATION MECHANISMS ................................................................. 47 4.2.1 Tritium .............................................................................................................................. 47 4.2.2 Fuel Leakage or External Contamination ......................................................................... 48 4.2.3 Cover Gas Handling System Contamination .................................................................... 48 4.2.4 Vessel Gasket Leakage ..................................................................................................... 48 4.2.5 Initial Material Loading .................................................................................................... 49 4.2.6 Maintenance Access ......................................................................................................... 49 4.2.7 PHX or DHX Tube Leakage ............................................................................................. 49 4.2.8 Fuel Moisture Contamination ........................................................................................... 49 4.2.9 Primary Coolant Pump Shaft Seal Leakage ...................................................................... 49 4.2.10 Thermowell Breakage ....................................................................................................... 49 4.2.11 Material (Bismuth) Carryover from the Primary Salt Cleanup System ............................ 50 4.2.12 Dissolved or Entrained Corrosion Product Activation ..................................................... 50 4.2.13 Fluorine Transmutation ..................................................................................................... 50 4.2.14 Reserve Shutdown System Activation .............................................................................. 50 4.3 FLUORIDE SALT CLEANING TECHNOLOGIES .................................................................. 50 4.3.1 Tritium .............................................................................................................................. 51 4.3.2 Particles ............................................................................................................................. 53 iii 4.3.3 Noble Gases ...................................................................................................................... 53 4.3.4 Noble and Seminoble Metals ............................................................................................ 54 4.3.5 Salt-Seeking Elements ...................................................................................................... 54 4.3.6 Iodine ................................................................................................................................ 55 4.3.7 Intermediate or DRACS Coolant ...................................................................................... 55 4.3.8 Corrosion Products ........................................................................................................... 55 4.3.9 Bismuth Carryover ............................................................................................................ 55 4.4 SALT CLEANUP SYSTEM INTEGRATION ............................................................................ 56 4.4.1 Flanges .............................................................................................................................. 56 4.4.2 Piping ................................................................................................................................ 57 4.4.3 Pumps ..............................................................................................................................
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