PREPARATION OF CHITOSAN-BASED MICROPOROUS COMPOSITE MATERIAL AND ITS APPLICATIONS
Microporous glutaraldehyde-crosslinked chitosan sorbents, methods of making and using them, and a generator for the radioisotope 99 Mo containing the sorbents.
1 . A sorbent comprising a microporous material comprising chitosan which has been crosslinked with glutaraldehyde in the presence of a catalyst to a glutaraldehyde concentration of about 2 to about 4 wt %, and which is resistant to degradation from exposure to beta and gamma radiation and from exposure to acids wherein the sorbent has been at least partially oxidized after crosslinking by an oxidizer selected from the group consisting of a chlorite, a hypochlorite, a dichromate, and a metal oxide.
2 . The sorbent according to claim 1 , wherein the sorbent has increased selectivity for the sorption of 99 Mo with respect to 99m Tc.
3 . The sorbent according to claim 1 , wherein the oxidizer is selected from the group consisting of an alkali metal chlorite, an alkali metal hypochlorite, an alkali metal dichromate, and a transition metal oxide.
4 . The sorbent according to claim 3 , wherein the oxidizer is selected from the group consisting of sodium chlorite, sodium hypochlorite, potassium dichromate, and cerium oxide.
5 . The sorbent according to claim 4 , wherein the oxidizer is selected from the group consisting of sodium chlorite and sodium hypochlorite.
6 . The sorbent according to claim 3 , wherein the surface charge of the sorbent when loaded with Mo(VI) is approximately zero at pH 3-4.
7 . The sorbent according to claim 1 , wherein the surface area of the sorbent ranges between 10 and 100 m 2 /g.
8 . The sorbent according to claim 7 , wherein the surface area of the sorbent is about 25 m 2 /g.
9 . The sorbent according to claim 1 , wherein the point of zero charge of the sorbent ranges from about 7.5 to about 8.8.
10 . The sorbent according to claim 1 , wherein the sorbent has a holding capacity for molybdenum that is from 5.4 to 6.25 mmol of molybdenum per gram of sorbent.
11 . A method for preparing a radiation-resistant sorbent, comprising:
combining chitosan with water in the presence of an acid to form a chitosan gel;
adding glutaraldehyde to the gel to form a semi-solid mass in the presence of catalyst at 70° C., in where condensation polymerization of reaction mass occurs;
washing the semi-solid mass to remove unreacted glutaraldehyde and form a washed mass;
suspending the washed mass in aqueous base to form a neutralized crosslinked mass;
drying the neutralized crosslinked mass to form the radiation-resistant sorbent; and
oxidizing the radiation-resistant sorbent with an oxidizer selected from the group consisting of a chlorite, hypochlorite, dichromate, or metal oxide.
12 . The method according to claim 11 , wherein the oxidizer is selected from the group consisting of an alkali metal chlorite, an alkali metal hypochlorite, an alkali metal dichromate, and a transition metal oxide.
13 . The method according to claim 12 , wherein said oxidizing comprises:
adding the oxidizer to the radiation-resistant sorbent at a pH between about 3 and about 11.
14 . The method according to claim 12 , wherein said oxidizing comprises contacting the oxidizer with the radiation-resistant sorbent for an exposure time from about 30 minutes to about 24 hours.
15 . The method according to claim 12 , wherein the concentration of oxidizer ranges from about 1 mM/L to about 10 mM/L, or where the ratio of solid to liquid is from around 1:100 to around 2:100, or both.
16 . A method of separating isotopes from mixtures thereof, comprising:
contacting a mixture of at least two isotopes with a radiation resistant sorbent according to claim 1 that preferentially sorbs at least one of said isotopes;
sorbing at least one of said isotopes onto or into said sorbent while one or more of the remaining isotopes are not significantly sorbed by the sorbent;
removing said one or more remaining isotopes from said sorbent.
17 . The method according to claim 16 , wherein said at least two isotopes comprise 99 MO and 99m TC.
18 . The method according to claim 17 , wherein said sorbent preferentially sorbs said 99 Mo and wherein said 99m Tc is not significantly sorbed by said sorbent.
19 . The method according to claim 16 , wherein one of said isotopes is a cesium isotope.
20 . The method according to claim 19 , wherein said one or more remaining isotopes comprise one or more isotopes present in a radioactive waste stream.
21 . The method according to claim 16 , wherein the removing of the one or more remaining isotopes from the sorbent comprises contacting the sorbent with an eluent solution.
22 . The method according to claim 21 , wherein the eluent solution comprises one or more oxidizers selected from the group consisting of a chlorite, a hypochlorite, a dichromate, and a metal oxide.
23 . A generator for 99 Mo/ 99m Tc, comprising the sorbent of claim 1 .
24 . A method for separating or concentrating or both one or more heavy metals from a liquid stream, comprising contacting a liquid stream containing said one or more heavy metals with a sorbent according to claim 1 , and sorbing one or more of said heavy metals thereon.