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

Technical Report · Wed Oct 01 00:00:00 EDT 2014

DOI:https://doi.org/10.2172/1237324· OSTI ID:1237324

Sun, Xiaodong ^[1]; Zhang, Xiaoqin ^[1]; Kim, Inhun ^[1]; O'Brien, James ^[2]; Sabharwall, Piyush ^[2]

---

1. The Ohio State Univ., Columbus, OH (United States)
2. Idaho National Lab. (INL), Idaho Falls, ID (United States)

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 chemistry 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.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1237324
• Report Number(s): INL/EXT-14-33562; TRN: US1600307
• Country of Publication: United States
• Language: English

Related Subjects

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