Heat Pipe Reactors (HPR) for space power conversion systems offer a number of advantages not easily provided by other systems. They require no pumping, their design easily deals with freezing and thawing of the liquid metal, and they can provide substantial levels of redundancy. Nevertheless, no reactor has ever been operated and cooled with heat pipes, and the startup and other operational characteristics of these systems remain largely unknown. Signification deviations from normal reactor heat removal mechanisms exist, because the heat pipes have fundamental heat removal limits due to sonic flow issues at low temperatures. This paper proposes an early prototypic test of a Heat Pipe Reactor (using existing 20% enriched nuclear fuel pins) to determine the operational characteristics of the HPR. The proposed design is similar in design to the HOMER and SAFE‐300 HPR designs (Elliot, Lipinski, and Poston, 2003; Houts, et. al, 2003). However, this reactor uses existing UZrH fuel pins that are coupled to potassium heat pipes modules. The prototype reactor would be located in the Sandia Annular Core Research Reactor Facility where the fuel pins currently reside. The proposed reactor would use the heat pipes to transport the heat from the UZrH fuel pins to a water pool above the core, and the heat transport to the water pool would be controlled by adjusting the pressure and gas type within a small annulus around each heat pipe. The reactor would operate as a self‐critical assembly at power levels up to 200 kWth. Because the nuclear heated HPR test uses existing fuel and because it would be performed in an existing facility with the appropriate safety authorization basis, the test could be performed rapidly and inexpensively. This approach makes it possible to validate the operation of a HPR and also measure the feedback mechanisms for a typical HPR design. A test of this nature would be the world’s first operating Heat Pipe Reactor. This reactor is therefore called “HPR‐1”.
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6 February 2005
SPACE TECHNOLOGY AND APPLICATIONS INT.FORUM-STAIF 2005: Conf.Thermophys in Micrograv;Conf Comm/Civil Next Gen.Space Transp; 22nd Symp Space Nucl.Powr Propuls.;Conf.Human/Robotic Techn.Nat'l Vision Space Expl.; 3rd Symp Space Colon.; 2nd Symp.New Frontiers
13-17 February 2005
Albuquerque, New Mexico (USA)
Research Article|
February 06 2005
Proposed Design and Operation of a Heat Pipe Reactor using the Sandia National Laboratories Annular Core Test Facility and Existing UZrH Fuel Pins
Steven A. Wright;
Steven A. Wright
Sandia National Laboratories, Org 6872 MS‐1146, PO Box 5800 Albuquerque, New Mexico 87185
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Ronald J. Lipinski;
Ronald J. Lipinski
Sandia National Laboratories, Org 6872 MS‐1146, PO Box 5800 Albuquerque, New Mexico 87185
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Tara Pandya;
Tara Pandya
Sandia National Laboratories, Org 6872 MS‐1146, PO Box 5800 Albuquerque, New Mexico 87185
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Curtis Peters
Curtis Peters
Sandia National Laboratories, Org 6872 MS‐1146, PO Box 5800 Albuquerque, New Mexico 87185
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AIP Conf. Proc. 746, 449–460 (2005)
Citation
Steven A. Wright, Ronald J. Lipinski, Tara Pandya, Curtis Peters; Proposed Design and Operation of a Heat Pipe Reactor using the Sandia National Laboratories Annular Core Test Facility and Existing UZrH Fuel Pins. AIP Conf. Proc. 6 February 2005; 746 (1): 449–460. https://doi.org/10.1063/1.1867161
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