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, Ronald J. Lipinski, Tara Pandya, Curtis Peters

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

10 Scopus citations

Abstract

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 kW th. 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".

Original languageEnglish
Title of host publicationSpace Technology and Applications International Forum - STAIF 2005, Including Co-located Conferences
Pages449-460
Number of pages12
DOIs
StatePublished - 2005
Externally publishedYes
EventSpace Technology and Applications International Forum: Forward with a New Age of Exploration, STAIF 2005 - Albuquerque, NM, United States
Duration: Feb 13 2005Feb 17 2005

Publication series

NameAIP Conference Proceedings
Volume746
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616

Conference

ConferenceSpace Technology and Applications International Forum: Forward with a New Age of Exploration, STAIF 2005
Country/TerritoryUnited States
CityAlbuquerque, NM
Period02/13/0502/17/05

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