Purification of molybdenum-99 by ion exchange chromatography

Symposium abstracts

258

3.

PRDTACTINIUM *,

**

M. SOLACHE-RIOS lnstituto National Ave. lnsurgentes

The development chemistry the

important

The of

are

isotope this

which

occurs

about

one ton

concentrated

hydrochloric

effects the

to

forming

break

materials

producing

the

growth

radioactivitv,

of

for

the

used

4.

of

the of

interest of

toward

of

this

was generated

protactinium.

and a wide

the

range

their

Much of preparation

of

compounds,

chemical

and

oroperties.

The currently

for

which

daughter its

chain

of

metallic

together

with

to

were

routes

provide

of

method

to

for

protactinium its

chemical

provided

of

preparation discussed

properties. the

preparative

comoounds

attention

protactinium

the

were

protactinium

particular

aloha

is necessary

storage

gram amounts

of

macro-quantities

investigations

physical

Si-0

fragments

and it

shielding

metal

had been

a few compounds

As a consequence of

of in

orotactinium

has been directed

Details

protactinium-231

of

acid

protactinium.

Due to of

and

in

scientists

and only

chemistry

the

gram amounts

partic!es.

tend

glass

containers,

01)

even

of

of

of

world-wide

in the

protactinium rapidly

chemistry

known.

element,

at

isolation

by English

availahilitv

containing

and colloidal

Radiation

absorb

were

in detectable uranium

containing

in

half-life

the

investigated

this

hydrolyse

polymers

bonds

of

the

little

mg.

Solutions to

longest

to

protactinium-231 1960,

protactinium-231

equilibrium

340

tend

the is

Nucleares YBxico, D. F.

Prior

among them,

following:

naturally

radioactive

3).-

protactinium

the

with

element

amounts;

2).-

the

has had many problems

most

l).-

of

de lnvestigaciones Sur 1079, 03720,

being

with

with

given

organic

to

complexes

ligands.

and manipulation

this

isotope.

PURIFICATION

OF MOLYBDENUM-99 BY ION EXCHANGE CHROMATOGRAPHY”

RAFAEL LOPEZ,

JUAN SERRANO AND LUZ ALICIA

FUCUGAUCHI

lnstituto National de lnvestigaciones Nucleares Ave. Insurgentes Sur 1079, 03720, Mixico, D. F.

In

the

this

a matrix of

preparation

of

radioisotope

the

235 U/AI

of fission

exchange

fission-product

is obtained followed

product

Mo-99,

hy irradiating bY separation

mixture

using

(MnO:‘).

Later

retained

by column

Thus,

and

the

a column AGlx8 with which

metallic MO-99

aluminum

is dissolved

resulting

solution

containing

the

is anion

(a styrene-divinylbenzene quaternary retains

amine the

functional

MO-99

matrix

eluted

in 4.5

H NaOH

passed

through

exchange

resin

copolymer groups)

as molybdate

is

eluted

has

been

with

1.5

H

H2S04 The

chromatography.

the

MO-99 which

ion retention

was 98% while

containing

the

ion

This

with

Ho-99

on the

recuperation

AGlx8 of

resin

MO-99

H2S04 was 93%.

separation

purification process.

of the

of

is MO-99

the

first

by this

step

in

production

the