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Massachusetts Institute of Technology

Polonium extraction techniques for a lead-bismuth cooled fast reactor

Abstract

dc:description.abstract

The construction of a next generation fast nuclear reactor using liquid lead-bismuth as a coolant demands the design of applied technology to remove 210Po from the neutron activated lead-bismuth eutectic. Experiments were performed to determine the kinetics of polonium hydride and lead-polonide released from molten lead-bismuth to determine the rate response of gaseous polonium chemical species in contact with various argon and hydrogen gas streams. It was determined that the rate release of polonium hydride is slightly higher at lower temperatures. The kinetic response is also faster with increased hydrogen content, as evident by the determined equilibrium constant. In addition, experiments involving the adsorption of gaseous polonium species on metallic praseodymium were undertaken. Formation of an oxidation layer and physical deterioration of the praseodymium inhibited proper sample analysis. The extraction techniques of rare-earth filtering and polonium hydride stripping and their relative figures of merit were discussed. Of the two techniques, a small-scale design adopting polonium hydride stripping was explored to address basic issues of design, fabrication, operation, and maintenance of an online polonium extraction system. Pending results of further investigation on alkaline extraction and electro-deposition experiments a small-scale design may be pursued.

Degree

thesis:*
Department dc:contributor.department
Massachusetts Institute of Technology. Department of Nuclear Engineering
Grantor dc:publisher
Massachusetts Institute of Technology
Year dc:date.issued
2002

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Larson, Christopher L. (Christopher Lee), 1978-
Advisor dc:contributor.advisor
  • Kenneth R. Czerwinski.

Subjects

dc:subject × 1

Rights

dc:rights
Statement dc:rights
  • M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.
Language dc:language.iso
eng

Identifiers

dc:identifier.*
Handle dc:identifier.uri
http://hdl.handle.net/1721.1/33825
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/33825

Chain of custody

source
Harvested from
MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Larson, Christopher L. (Christopher Lee), 1978-. Polonium extraction techniques for a lead-bismuth cooled fast reactor. Massachusetts Institute of Technology, 2002. http://hdl.handle.net/1721.1/33825