TY - JOUR
T1 - Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor—Part I
AU - Sabharwall, Piyush
AU - Weaver, Kevan
AU - Anand, N. K.
AU - Ellis, Chris
AU - Sun, Xiaodong
AU - Chen, Di
AU - Choi, Hangbok
AU - Christensen, Rich
AU - Fronk, Brian M.
AU - Gess, Joshua
AU - Hassan, Yassin
AU - Jovanovic, Igor
AU - Manera, Annalisa
AU - Petrov, Victor
AU - Vaghetto, Rodolfo
AU - Balderrama-Prieto, Silvino
AU - Burak, Adam J.
AU - Burger, Milos
AU - Cardenas-Melgar, Alberto
AU - Garrett, Londrea
AU - Gaudin, Genevieve L.
AU - Orea, Daniel
AU - Chavez, Reynaldo
AU - Choi, Byunghee
AU - Sutton, Noah
AU - Williams, Ken
AU - Young, Josh
N1 - Publisher Copyright:
© 2022 The Author(s). Published with license by Taylor & Francis Group, LLC.
PY - 2022
Y1 - 2022
N2 - An integrated effort by the Versatile Test Reactor (VTR) Gas-Cooled Fast Reactor (GFR) Team to develop an experiment vehicle or extended-length test assembly for the VTR experiments is led by the Idaho National Laboratory and supported by an industrial partner, General Atomics, and university partners, including Texas A&M University, University of Michigan, Oregon State University, University of Houston, and University of Idaho. The overall focus of the effort is to design a helium gas-cooled cartridge loop (GCL) to assist with the testing of fuels, materials, and instrumentation to further support development of advanced reactor systems. This study is divided into two parts. Part I provides the GCL functional requirements and critical irradiation data needs for advancing GFR technologies. Part II includes the measurement techniques developed to measure the thermophysical properties of the different materials in the GCL, as well as the functionality and efficacy of these instrumentation and control systems within the GCL. This paper, Part I, describes the overall preliminary conceptual design of the VTR helium cartridge loop, the design of a fission product venting system, the thermal-hydraulic effects of flow direction, and gamma-heating generation in the cartridge. This paper also describes a three-dimensional computational fluid dynamics study that was carried out to examine the effects of the helium flow direction in the GCL on its thermal-hydraulic characteristics, engineering feasibility, and in-VTR experiment design. Both steady-state operation and a transient scenario (pressurized loss of forced circulation) were analyzed for the upward and downward helium flow options in the test article section in the GCL to provide quantitative data for selection of the helium flow direction. Additional analyses and development, as well as integrated out-of-pile testing, are planned to demonstrate and verify the performance of the GCL prior to insertion into the VTR.
AB - An integrated effort by the Versatile Test Reactor (VTR) Gas-Cooled Fast Reactor (GFR) Team to develop an experiment vehicle or extended-length test assembly for the VTR experiments is led by the Idaho National Laboratory and supported by an industrial partner, General Atomics, and university partners, including Texas A&M University, University of Michigan, Oregon State University, University of Houston, and University of Idaho. The overall focus of the effort is to design a helium gas-cooled cartridge loop (GCL) to assist with the testing of fuels, materials, and instrumentation to further support development of advanced reactor systems. This study is divided into two parts. Part I provides the GCL functional requirements and critical irradiation data needs for advancing GFR technologies. Part II includes the measurement techniques developed to measure the thermophysical properties of the different materials in the GCL, as well as the functionality and efficacy of these instrumentation and control systems within the GCL. This paper, Part I, describes the overall preliminary conceptual design of the VTR helium cartridge loop, the design of a fission product venting system, the thermal-hydraulic effects of flow direction, and gamma-heating generation in the cartridge. This paper also describes a three-dimensional computational fluid dynamics study that was carried out to examine the effects of the helium flow direction in the GCL on its thermal-hydraulic characteristics, engineering feasibility, and in-VTR experiment design. Both steady-state operation and a transient scenario (pressurized loss of forced circulation) were analyzed for the upward and downward helium flow options in the test article section in the GCL to provide quantitative data for selection of the helium flow direction. Additional analyses and development, as well as integrated out-of-pile testing, are planned to demonstrate and verify the performance of the GCL prior to insertion into the VTR.
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U2 - 10.1080/00295639.2022.2070383
DO - 10.1080/00295639.2022.2070383
M3 - Article
AN - SCOPUS:85133613194
SN - 0029-5639
VL - 196
SP - 183
EP - 214
JO - Nuclear Science and Engineering
JF - Nuclear Science and Engineering
IS - sup1
ER -