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Title: The Development of an INL Capability for High Temperature Flow, Heat Transfer, and Thermal Energy Storage with Applications in Advanced Small Modular Reactors, High Temperature Heat Exchangers, Hybrid Energy Systems, and Dynamic Grid Energy Storage C

The overall goal of this project is to support Idaho National Laboratory in developing a new advanced high temperature multi fluid multi loop test facility that is aimed at investigating fluid flow and heat transfer, material corrosion, heat exchanger characteristics and instrumentation performance, among others, for nuclear applications. Specifically, preliminary research has been performed at The Ohio State University in the following areas: 1. A review of fluoride molten salts’ characteristics in thermal, corrosive, and compatibility performances. A recommendation for a salt selection is provided. Material candidates for both molten salt and helium flow loop have been identified. 2. A conceptual facility design that satisfies the multi loop (two coolant loops [i.e., fluoride molten salts and helium]) multi purpose (two operation modes [i.e., forced and natural circulation]) requirements. Schematic models are presented. The thermal hydraulic performances in a preliminary printed circuit heat exchanger (PCHE) design have been estimated. 3. An introduction of computational methods and models for pipe heat loss analysis and cases studies. Recommendations on insulation material selection have been provided. 4. An analysis of pipe pressure rating and sizing. Preliminary recommendations on pipe size selection have been provided. 5. A review of molten fluoride salt preparation and chemistrymore » control. An introduction to the experience from the Molten Salt Reactor Experiment at Oak Ridge National Laboratory has been provided. 6. A review of some instruments and components to be used in the facility. Flowmeters and Grayloc connectors have been included. This report primarily presents the conclusions drawn from the extensive review of literatures in material selections and the facility design progress at the current stage. It provides some useful guidelines in insulation material and pipe size selection, as well as an introductory review of facility process and components.« less
Authors:
 [1] ;  [1] ;  [1] ;  [2] ;  [2]
  1. The Ohio State Univ., Columbus, OH (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1237324
Report Number(s):
INL/EXT--14-33562
TRN: US1600307
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE; NATURAL CONVECTION; FORCED CONVECTION; MOLTEN SALTS; HEAT LOSSES; COOLANT LOOPS; HELIUM; TEMPERATURE RANGE 0400-1000 K; FLUORIDES; HEAT EXCHANGERS; HEAT STORAGE; RECOMMENDATIONS; MSRE REACTOR; THERMAL HYDRAULICS; CONNECTORS; DESIGN; FLOWMETERS; PERFORMANCE; PRINTED CIRCUITS; CORROSION; HYBRID SYSTEMS; ENERGY STORAGE; FLUID FLOW; TEST FACILITIES; CHEMICAL REACTIONS; COMPATIBILITY; CONTROL; OPERATION; SIZE; MODULAR STRUCTURES; PIPES; CALCULATION METHODS; MATHEMATICAL MODELS; THERMAL INSULATION; POWER SYSTEMS; TEMPERATURE DEPENDENCE; CHEMICAL PREPARATION