How To Make Molybdenum 99
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1 IAEA-TECDOC-1065 XA Production technologies for molybdenum-99
2 The originating Section of this publication in the IAEA was: Industrial Applications and Chemistry Section International Atomic Energy Agency Wagramer Strasse
3 The IAEA does not normally maintain stocks of reports in this series. However, copies
4 Nuclear medicine FOREWORD
5 EDITORIAL NOTE In preparing this publication for press, staff of the IAEA have made up the pages from the original manuscripts
6 CONTENTS Surrimaiy...^ Characteristics of nuclear reactors used for the production of molybdenum R.M. Ball Targets
7 SUMMARY Technetium-99m (6.02 h) is the most widely used radioisotope in nuclear medicine, accounting
8 The presently installed processing capacity is substantially larger than the above mentioned demand,
9 photon radiopharmaceuticals (i.e.
10 CHARACTERISTICS XA
11 In practice, one cannot productively capture all the neutrons available and a comparison among reactor types, shown later,
12 with
13 TABLE I. CHARACTERISTICS OF REACTORS USED TO IRRADIATE TARGETS FOR "MO PRODUCTION Reactor Name Location Power kwth Flux nvth Target Vol. cm 3 (1 tar.) NRU Canada 135, E HFR Netherlands 45, E ACRR USA 2, E HFIR USA 85, E15 TRIGA USA 2, E13 MURR USA 10, E14 -- SAFARI- 1 South Africa 20, E14 HIFAR Australia 10, E NRU Reactor This reactor
14 quantities of "Mo have been made in The reactor is owned and operated under contract for the U.S. Department of Energy. It is stated to be a "backup" for other commercial sources of "Mo HFIR Reactor
15 1.4. Heat removal requirements for targets used to make "Mo Irradiation of 98 Mo Targets The deposition of energy in
16 (3) By using daily extraction of "Mo, eliminates the unrecoverable losses from target decay within the reactor (see Figure 1). (4) Reduces the amount of fission product waste produced by a factor of 100 and stores long lived wastes within the reactor solution. (5) Requires only the
17 FIG
18
19 NONE Required Target Preparation NOT Required Encapsulate Ship FIG. 5. Process cycle using solution (MIPR) system. 8»
20 Downscaling the MIPR for Lower Production Requirements Some developing countries may desire a lower production rate, perhaps 8000 GBq week" 1. With three days of production, the reactor could be operated at less than 10 kw. The amount of uranium and the hardware requirements for reactor operation are much the same but the consumption of consumables and the production of radioactive waste are greatly reduced Uranium Consumption
21 S200/Curie
22 If a MIPR system were constructed with investment capital, the costs for the product must include repayment and interest. The other costs are variable costs associated the level of production.
23 TARGETS FOR THE PRODUCTION OF NEUTRON ACTIVATED MOLYBDENUM-99 XA E.L.R. HETHERINGTON, R.E. BOYD Australian Nuclear Science
24 2. TARGET CHARACTERISTICS Natural molybdenum consists of seven stable isotopes; neutron activation gives rise to only three molybdenum radioisotopes
25 TABLE II. PRODUCTION OF "Mo BY NEUTRON IRRADIATION OF MOLYBDENUM TRIOXIDE IN THE ANSTO RESEARCH REACTOR HIFAR Reactor Type 10
26 [4] NARASHIMAN, D.V.S., VANAJA, P, IYER, S.P., MANI, R.S., Development of a new
27 PURIFICATION ANNEX
28 XA CONVERTING TARGETS AND PROCESSES FOR FISSION-PRODUCT MOLYBDENUM-99 FROM HIGH- TO LOW-ENRICHED URANIUM G.F. VANDEGRIFT, J.L. SNELGROVE, S. AASE, M.M. BRETSCHER, B.A. BUCHHOLZ,
29 performance, economics,
30 TABLE
31 TABLE
32 TABLE
33 TABLE II. (Cont.) Major Technical Challenges to LEU Substitution (Continued) Specific Acid Dissolution Process Base Dissolution
34 TABLE II. (Cont.) Means Convert to Acid Dissolution Process Base Dissolution
35 TABLE II. (Cont.) Means Acid Dissolution Process Base Dissolution
36 TABLE II. (Cont.) Status Acid Dissolution Process Base Dissolution
37 TABLE H. (Cont.) Status Acid Dissolution Process Base Dissolution
38 In
39
40 Postirradiation examinations performed during April and May of 1996 showed that the uranium foil was bonded to the inner tube of each of these targets. The tentative explanation
41 The latter two targets demonstrated the viability of the fission-fragment-barrier concept. Another series
42 surface preparation has been extremely challenging. We must balance surface roughness against dissolution of the foil. We have used an alkaline zincate bath for plating zinc, an alkaline copper phosphate bath
43 FIG. FIG. 3. SEM photograph showing nodular nature of Zn plate.
44 FIG. 5. Early Zn-plated uranium foil showing considerable loss of uranium during etching. FIG.
45 FIG.7. Two examples of acceptable zinc-plated uranium foils. Scanning electron micrographs of an early attempt at plating uranium with zinc barriers are shown
46 Surface preparation is a compromise between optimal conditions for making a uniform
47 Target dissolution The Cintichem HEU target is a closed cylinder with an electrodeposited layer of UO
48 positive. This gave a a of , a 33 of , a n! of , a n2 of , a sl of , a s2 of ,
49 10 o c 1 Nitric acid is 3M in all cases S 1 03 EC _o *3 _=> O V) V) 1M Sulfuric Acid 2M Sulfuric Acid FIG looon; I/K -t-
50 TO In a ct^ 3 (A in 0) ^ a. w ffi > o in in tuu A l\ < >* 1 I 1 ' f. I * *, f il '/,', I ' /' ''" 'I* '(. I ' -D g.BAT AN
51 compound. Although we have been developing the Zn-barrier foils for basic dissolution, using it for acid-side processing is certainly possible if the dissolution rate can be easily handled by increasing dissolver temperature. Further details
52 volume
53 FIG.
54 TABLE
55 In summary, our experimental results predict that replacing the current dissolution cocktail, which contains both nitric and sulfuric acids, with nitric acid alone will not compromise the effectiveness of the Cintichem process. In our tracer experiments with this substitution, molybdenum recovery and purity were not degraded. Removal of sulfuric acid from
56 An important side reaction that occurs during the silicide dissolution process is the autodestruction of hydrogen peroxide: 6 2H 2 O 2
57 is considered. The different activation energies for the two particle types show that more than surface area differences are relevant in the dissolution kinetics of atomized and comminuted U 3 Si 2 particles. 100 a. -29 D C, CO --*--50 C,CO - r 50 C,AT -» C, CO o Initial NaOH Concentration (mol
58 or 160=[H0 2-3[H 2 0] = [HQJ] [H ][OH~] [H ][OH-] Figure 14 plots the equilibrium concentrations of O 2 H~, OH", and H 2 O 2 for a fixed initial peroxide concentration of 5.2M H 2 O 2 and variable initial OH" concentrations. In basic solution the equilibrium H 2 O 2 concentration
59 Eventually, through a series of fast reactions, complex B becomes the soluble form of uranium that
60 Dissolving unirradiated U
61 Cladding precipitates must
62 Design of a dissolver system for a two-step process that also provides physical desegregation is a difficult technical problem. This among other problems led us to suspend activity in this area and look toward other targets Uranium-foil targets We first dissolved uranium foil
63 this basis,
64 10" o» * J o Cfl C/3 S -r IO' 5 Z <OS 3 b O a < 65 lo' 7
65 10'= on u. O UJ O 2 UJ 0. Q. E o "o E 10" Various Base 0.2M NaOH LOMNaOH 5.0M NaOH li. O UJ 10' 10' 10"' 10 [H 2 O 2 ] AT EQUILIBRIUM (M) FIG.
66 Based
67 An optimized procedure
68 foil. Zinc is an active electropositive element and forms a strong anion with oxygen. It also dissolves readily in sodium-hydroxide/nitrate solution. Work on barrier materials for targets to be processed
69 Solutions suitable for dissolving the intermetallic U/Zn compound were pursued. Attempts to dissolve the zinc from this foil showed that this intermetallic would not dissolve as the zinc plate had from the unheated foils (at 70 C with 50 ml of 2.5M NaOH and 1M NaNO 3 ).
70 aluminum dissolution. Finally,
71 irradiated
72 Alummum/UO Dispersion Aluminum Cladding Dispersion FIG. 22. Illustration of a UO 2 /AI-dispersion plate and micrograph of a UO 2 /Al-dispersion compact. Molybdenum recovery was high, and purification was as expected when the two-step dissolution was followed by acidification and molybdenum sorption on an alumina column. Because
73 Once conditions for LEU target dissolution are firm, we will need to reinvestigate the effects of these compositional and volume differences on the primary molybdenum-recovery step. 6. PLANNED R&D ACTIVITIES We will continue our development activities on both acid- and base-side processes. The LEU-modified Cintichem process needs
74 [6] SAMEH, A.A., ACHE, H.J., "Production Techniques of Fission 99 Mo", Fission Molybdenum for Medical Use, Proc. of Technical Committee Mtg. Organized by the International Atomic Energy Agency, Karlsruhe, October 13-16, 1987, IAEA-TECDOC-515 (1989) [7] SALACZ, J., "Processing of Irradiated
75 [19] LUNDQUIST, J.R., BRAUN, R.L., STROMATT, R.W., "Nickel Plating Uranium: Review
76 LEU Targets for "Mo Production Demonstration of a Modified Cintichem Process", Proceedings
77 [48] HOFMAN, G.L., NEIMARK, L.A., OLQUIN, F.L, "The Effect
78 THE ACCELERATOR PRODUCTION XA
79 that A comparison of the experimental production yields reported in the literature indicates
80 3. RESULTS
81 100 Mo -f p Proton Energy / MeV FIG.
82 100 Mo + p 99i. (p.pn^mo 98ji (p,p2n) ah Mo c CO (p,p4n) 96 Mo (p,p3n) 97 Mo Proton Energy / MeV FIG.
83 potential accelerator production
84 IS 20 2S JO JJ SO W SO S3 70 o \ O 0 S O +S SO IS 60 6S 70
85 100i Mo
86
87 [2] Further steps to ensure moly-99 supply, J. Nucl. Med. 37 (1996) 34N.
88 [22] BLANN M., VONACH H.K., Global test of modified precompound decay models, Phys. Rev. C28 (1983) [23] MYERS W.D., SWIATECKI W., Anomalies in nuclear masses, J. Ark. Fys. 36 (1967) [24] SCHOLTEN
89 ACCELERATOR PRODUCTION OF 99m Tc WITH PROTON BEAMS XA
90 have suffered from minor
91 and should be able to withstand high current bombardments. The natural and enriched 98 Mo(VI) oxide (MoO 3. d= g/cm 3 ; m.p. 795 C; b.p C sub.) were used only in experiments conducted with low intensity beams (< 1 ya), as the Mo oxide is not an appropriate target material for high intensity bombardments. Other chemical forms of Mo were
92 similar enriched IOO Mo thick target
93 (BOB).
94 TABLE
95 TABLE III. REACTION CHANNELS
96 97 Mo, 96 Mo, 95 Mo and 94 Mo as target nuclides in the enriched 100 Mo targets, was minimized by using
97 each thin
98 TABLE IV. (Cont.) Proton Energy (MeV)
99 TABLE
100 > ' c o /3 co s u Experimental Data ""Fit Proton Energy (MeV) FIG. 2. Excitation function for the nat Mo(p,xn) 96 Tc reaction. 1500
101
102 However, the precision of the yield estimates for 96 Tc, 95 Tc, and 94 Tc, produced by the unfolding method, needed further testing (see section 3.4, below). Further analysis of the yield data
103 TABLE V. (Cont.) Target Energy (MeV) 16.0 ± ± ± ± ±
104
105 Experimental Data ""Fit Proton Energy (MeV) FIG.
106 TABLE VI. COMPARISON OF MEASURED AND CALCULATED To WITH 20.5 AND ^Tc YIELDS PRODUCED
107 Further experimental testing with a MeV thick
108 medical use. Technetium-96 (4.35
109 Tc-99m (140.5 kev) Gamma-ray Energy (kev) 450 FIG. 9. Gamma-ray spectrum of accelerator-produced 99m Tc from anenriched!00 Mo (CIS; 97.46%) thick ( MeV) target Radioassay at 25 h after BOB Tc-99m (140.5 kev) I u ( FIG Gamma-ray Energy (kev)
110 iu - au ex 3 O U Tc-94 (702.6 kev) \ c i CD cm "; "-'- Tc-95 (766 kev) p p oo on\ o cxfn <nno Tc-96 (849.9 kev) H O OOO QDO OD
111 cumulative 99m Tc yields per target were extrapolated to higher beam intensities and target power using enriched 100 Mo (97.46%). Results
112 I c o S 40 C/3 00 o u
113 depending on foreign supply based on the operation of few commercial reactors, and many at present rely on aging reactor facilities facing decommissioning. Accelerator facilities capable
114 [9] LAGUNAS-SOLAR, M.C. et al, "An update on the direct production of Tc-99m with proton beams and enriched Mo-100 targets". Annual Meeting of the American Nuclear Society (June 16-20, 1996), Reno, Nevada, USA. [10] EGAN G., JAMIESON, C., LAGUNAS-SOLAR, M.C., An investigation into the technical feasibility
115 EXCITATION FUNCTIONS XA
116 In the second part we present the results of our calculations concerning production yields
117 TABLE I. NUCLEAR DATA OF THE REACTIONS Nuclide Half life Molybdenum 101 Mo 14.6
118 TABLE I. (Cont.) Nuclide Half life 97 Tc 2.6*
119 TABLE I. (Cont.) Nuclide Half life Decay mode Niobium "Nb 15.0s P"(100) 99n Nb
120 TABLE I. (Cont.) Nuclide Half life 94m Nb 6.26
121 Cross-section [mb]
122 3.2.
123 Cross-section [mb] Cross-section [mb] c A 01 p [V. 0 yoen C/J en -» o> o o' g1 3 (B O^ ^ S 1 (-3 s -s 5. o P" <n ^^ A TO H p W o ro
124 to Cross-section [mb] w ; S en P ON O 3en en en.* 8«h o" U >3 O t. J O *< i 1 o "x 4" M
125 The excitation curve (Fig.5) shows two contributing reactions: 94 Mo(d,2n) (Q 7.34 MeV) and 95 Mo(d,3n) (Q= MeV), where the (d,2n) reaction on the less abundant 94 Mo (9.25 %) reaches a maximal cross section value near 16 MeV, making this the optimal production path using deuteron induced reactions below 21 MeV. From our measured cross section values a physical yield of 3545 MBq/mAh (95 mci/uah) is calculated for the energy range 12-17
126 Cross-section [mb] Cross-section [mb] o < -i. _L O SO 01 O < o o o < n HH P CO 0 3cn cn cn 8 3?. G 1 o 5 3 <3 0 '2 "x u! "~"«2*. I *? > -is Ol " j o ^0 % > ^^ "5 * i» 00 H p o ro at
127 Cross-section [mb] g & 8 Cross-section [mb] ro
128
129 investigate
130 TABLE II. DEUTERON INDUCED REACTIONS ON ENRICHED
131 Production yield
132 reactions 100 Mo(p,2n) 99m Tc and 100 Mo(p,pn)"Mo on Fig. 11 for comparison. The yields for proton were calculated from
133
134 HIGH BEAM INTENSITIES FOR CYCLOTRON-BASED RADIOISOTOPE PRODUCTION XA
135 internal P.LG. source,
136 sources. The adopted solution of an external H" source with its own pumping system allows the neutral gas to be pumped in the external source system, and moderate size pumps are sufficient
137 As
138 an extraction system allowing
139
140 ADONIS: THE PROTON-DRIVEN NEUTRON SOURCE FOR RADIOISOTOPE PRODUCTION XA Y. JONGEN Ion Beam Applications s.a., Louvain-la-Neuve, Belgium Abstract 99 The world production of fission Mo is today made in a very small number of research reactors which are getting quite old and are due, in the next years, for a major refurbishment or for decommissioning.
141 99 continue to use the existing and very expensive fission Mo chemical separation facilities, and
142
143 ^0^0 a H B D^0^ao^o^ e 3 ^ =& f E R,VoVflYnVn avii o 0 & o o ov^^ 3 > tj<j=j Wta,,1 I,. 1 1 i i. D m m Sl I will i i,-,-^jijjf 1 1
144 Fig. 2. Positioning of the uranium targets 143
145 All the above components are located in a main irradiation pool, for moderation and shielding purposes. Adjacent to the main pool is an annex pool (see Fig.l) allowing the remote handling
146 Fig. 3. Neutron flux distribution The maximum total production corresponds, at the end, to more than 50% of the world's demand, while the obtained mean specific activities are comparable to those presently obtained
147 [2] JONGEN, Y., "A Proton-Driven, Intense, Sub-critical, Fission Neutron Source for Radioisotope Production", International Conference on Accelerator-Driven Transmutation Technologies and Applications, Las Vegas, NV, July [3] MC ADAMS, R., KING, R.F., PROUDFOOT, G., HOLMES, A.J.T., "Pure and Cesiated CW Volume Source Performance at the Culham Ion Source Test Stand", Proceedings of Sixth Intl. Symposium
148 THE XA
149 Although some general comments
150 150g Mo03 Irrad. 7x10* 3 n/cm2/sec 7 days Dissolve in m NaOH
151 then another range of much higher radioactivities typical of those used in centralised radiopharmacies (the "jumbo" generators). A comprehensive program of performance testing
152 4.3. Other radionuclidic impurities After the short-lived radioactivities had decayed (a few days), several of the eluateswere re-examined for the presence (identity and concentration) of other radionuclidic impurities.
153 4.5. Radiochemical Purity Radiochemical impurities often arise due to the effects of radiation on the solvent(radiolysis), changes in temperature or ph, or the presence of reducing/oxidising agents. The pertechnetate ion is a strong oxidising agent capable of reacting with traces of reducing substances to produce lower valency species. Using thin layer chromatographic techniques the radiochemical species present in the eluates were investigated (Table VI) Elution Profile The elution profile of column based generators is influenced strongly by physical size and shape [6].
154 FIG. 2. The effect of bed size on the elution profile Clinical experience
155 The gaseous releases from
156 REFERENCES [1] COATS, R.L., "The "Mo Production Program at Sandia National Laboratories", Proc. Conf. American Nuclear Society, (Philadelphia, June 1995). [2] LAGUNAS-SOLAR, M. et al, Cyclotron production of NCA 99m Tc and "Mo. An alternative non-reactor supply source of instant " m Tc and "Mo, Appl. Radial. Isot. 42 (1991) [3] JONGEN, Y., "A Proton-Driven, Intense, Sub-critical, Fission Neutron Source for Radioisotope Production", Accelerator-Driven Transmutation Technologies
157 LIST
158 Vandegrift, G.F. Argonne National Laboratory, Argonne, Illinois, United States of America Vera Ruiz,
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