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Title: Automated product recovery in a Hg-196 photochemical isotope separation process

Abstract

A method of removing deposited product from a photochemical reactor used in the enrichment of [sup 196]Hg has been developed and shown to be effective for rapid re-cycling of the reactor system. Unlike previous methods relatively low temperatures are used in a gas and vapor phase process of removal. Importantly, the recovery process is understood in a quantitative manner so that scaling design to larger capacity systems can be easily carried out. 2 figs.

Inventors:
;
Issue Date:
OSTI Identifier:
7274482
Patent Number(s):
5131991 A
Application Number:
PPN: US 7-708797
Assignee:
GTE Products Corp., Danvers, MA (United States) PTO; EDB-94-089911
DOE Contract Number:  
AC03-76SF00098
Resource Type:
Patent
Resource Relation:
Patent File Date: 30 May 1991
Country of Publication:
United States
Language:
English
Subject:
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; MERCURY 196; ISOTOPE SEPARATION; AUTOMATION; CHEMICAL REACTORS; MATERIALS HANDLING EQUIPMENT; MATERIALS RECOVERY; PHOTOCHEMICAL REACTIONS; CHEMICAL REACTIONS; EQUIPMENT; EVEN-EVEN NUCLEI; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; MERCURY ISOTOPES; NUCLEI; PROCESSING; SEPARATION PROCESSES; STABLE ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; 400703* - Radiochemistry & Nuclear Chemistry- Radioisotope Production

Citation Formats

Grossman, M.W., and Speer, R. Automated product recovery in a Hg-196 photochemical isotope separation process. United States: N. p., 1992. Web.
Grossman, M.W., & Speer, R. Automated product recovery in a Hg-196 photochemical isotope separation process. United States.
Grossman, M.W., and Speer, R. Tue . "Automated product recovery in a Hg-196 photochemical isotope separation process". United States.
@article{osti_7274482,
title = {Automated product recovery in a Hg-196 photochemical isotope separation process},
author = {Grossman, M.W. and Speer, R.},
abstractNote = {A method of removing deposited product from a photochemical reactor used in the enrichment of [sup 196]Hg has been developed and shown to be effective for rapid re-cycling of the reactor system. Unlike previous methods relatively low temperatures are used in a gas and vapor phase process of removal. Importantly, the recovery process is understood in a quantitative manner so that scaling design to larger capacity systems can be easily carried out. 2 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {7}
}