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Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear

Abstract

The tritium is a radioisotope that can be used to carry out basic as applied research. The current researches on the labelling of the organic molecules as well as its application in diagnostic, radiotherapy and hydrology among others confirm the before said. Due to their utility, they have been carried out studies to recover it of radioactive or nuclear waste as well as, to concentrate it of the natural water, the one which due to the nuclear tests in the last decades has gotten rich in tritium. In this work previous studies to recover the tritium coming from the process that was used to produce F-18 following the reaction {sup 6} Li (n, {alpha}) {sup 3} H, {sup 16} O (t, n) {sup 18} F in made up of lithium oxygenated, in the TRIGA Mark III Nuclear Reactor of the Nuclear Center of Mexico. The method consists on purifying by ion exchange the waste solutions where F-18 took place, to distill them and to concentrate them for an electrochemical method. It was already adapts a system reported to concentrate big volumes (approximately 250 ml) in such a way that could be used for small volumes. It was recovered 30% of  More>>
Publication Date:
Sep 15, 1990
Product Type:
Technical Report
Report Number:
Q-90-02; INIS-MX-RI-0156
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; DIAGRAMS; ELECTROCHEMISTRY; EXPERIMENTAL DATA; FLUORINE 18; ION EXCHANGE CHROMATOGRAPHY; LITHIUM CARBONATES; NUCLEAR REACTIONS; TRIGA-3-SALAZAR REACTOR; TRITIUM RECOVERY
OSTI ID:
20783707
Research Organizations:
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac (Mexico)
Country of Origin:
Mexico
Language:
Spanish
Other Identifying Numbers:
TRN: MX0600197086959
Availability:
Available from INIS in electronic form
Submitting Site:
MXN
Size:
48 pages
Announcement Date:
Jan 14, 2010

Citation Formats

Flores R, H, Palma G, F A, and Ramirez, F M. Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear. Mexico: N. p., 1990. Web.
Flores R, H, Palma G, F A, & Ramirez, F M. Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear. Mexico.
Flores R, H, Palma G, F A, and Ramirez, F M. 1990. "Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear." Mexico.
@misc{etde_20783707,
title = {Tritium recovery as waste sub product in the Fluorine 18 production in a nuclear reactor; Recuperacion de tritio como subproducto de desecho en la produccion de F-18 en un reactor nuclear}
author = {Flores R, H, Palma G, F A, and Ramirez, F M}
abstractNote = {The tritium is a radioisotope that can be used to carry out basic as applied research. The current researches on the labelling of the organic molecules as well as its application in diagnostic, radiotherapy and hydrology among others confirm the before said. Due to their utility, they have been carried out studies to recover it of radioactive or nuclear waste as well as, to concentrate it of the natural water, the one which due to the nuclear tests in the last decades has gotten rich in tritium. In this work previous studies to recover the tritium coming from the process that was used to produce F-18 following the reaction {sup 6} Li (n, {alpha}) {sup 3} H, {sup 16} O (t, n) {sup 18} F in made up of lithium oxygenated, in the TRIGA Mark III Nuclear Reactor of the Nuclear Center of Mexico. The method consists on purifying by ion exchange the waste solutions where F-18 took place, to distill them and to concentrate them for an electrochemical method. It was already adapts a system reported to concentrate big volumes (approximately 250 ml) in such a way that could be used for small volumes. It was recovered 30% of the considered initial quantity of tritium. A modification to the proposed methodology will allow to recover the waste tritium in a percentage greater to 80%. (Author)}
place = {Mexico}
year = {1990}
month = {Sep}
}