WorldWideScience
 
 
2

Production and evaluation of labeled bisphosphonates with 153Sm, 166Ho and 177Lu as therapeutic radiopharmaceuticals  

International Nuclear Information System (INIS)

Aim: Compounds such "9"9"mTc-MDP and "9"9"mTc-HEDP are used regularly in bone scintigraphy for metastasis detection. The therapeutics properties of beta emitter radionuclides like "1"5"3Sm, "1"6"6Ho and "1"7"7Lu has been widely reported in literature being "1"7"7Lu the less developed for medical applications. With the purpose of study different radiopharmaceuticals alternatives, for metastasis bone palliation, we have evaluated, on a comparative basis, the labeling of "1"5"3Sm-MDP, "1"5"3Sm-HEDP, "1"6"6Ho-MDP, "1"6"6Ho-HEDP, "1"7"7Lu-MDP and "1"7"7Lu-HEDP from the exhibited radionuclidic purity and biological distribution point of view. Material and Methods: The radionuclides were produced at La Reina Research Reactor, Chilean Nuclear Energy Commission. The radionuclidic purity was determined by gamma-Ray spectrometry. The labeling was accomplished with MDP (Plenum) and HEDP synthesized in-house. The in-vitro affinity of labeled compounds to the mineral bone matrix was determined using ...

2002-09-01

3

Modification of NPL-CRC secondary standards radionuclide calibrator holder to suit for IPEN vials  

International Nuclear Information System (INIS)

The procedure followed by the Laboratorio de Metrologia Nuclear (LMN) at the IPEN - CNEN/SP, in Sao Paulo, for modifying the NPL-CRC radionuclide sample holder in order to adapt for IPEN vials is presented. For the quality assurance of the results using the IPEN vials, the influence of variation in dimensions and volume of solution has been investigated and suitable correction factors were applied. The solutions used in the present work were "5"1Cr "9"9"mTc "1"5"3Sm, and "2"0"1Tl. (author)

2000-10-05

4

Radiochemical separation of no-carrier-added {sup 177}Lu as produced via the {sup 176}Ybn,{gamma}{sup 177}Yb{yields}{sup 177}Lu process  

Energy Technology Data Exchange (ETDEWEB)

The {sup 176}Ybn,{gamma}{sup 177}Yb-{beta}{sup -}{yields}{sup 177}Lu process was investigated to provide no-carrier-added (nca) {sup 177}Lu. The radiochemical separation of the {sup 177}Lu from the macro-amounts of the ytterbium target based on the cementation process, i.e. the selective extraction of Yb by Na(Hg) amalgam from Cl{sup -}/CH{sub 3}COO{sup -} electrolytes, followed by a final cation exchange purification. The cementation separation process provides a decontamination factor of Yb(III) of 10{sup 4}, the cation exchange purification adding a decontamination factor of >10{sup 2}. The nca {sup 177}Lu is available in radiochemically pure form despite the chemical similarity of the lanthanides with 75{+-}5% overall separation yield within 4-5 h. It can be used to synthesise nca {sup ...

2000-09-15

5

Excitation functions for proton-induced reactions on natural hafnium: Production of {sup 177}Lu for medical use  

Energy Technology Data Exchange (ETDEWEB)

There is an increasing interest in using radioisotopes of rare earth elements for internal radiotherapy and for imaging in nuclear medicine. {sup 177}Lu is one of the promising radionuclides. This article reports on the first measurements of the excitation function for the production of {sup 177}Lu with proton-beam energies up to 17 MeV on natural hafnium targets. The experimental cross sections for the reaction {sup nat}Hf(p,x){sup 177}Lu were obtained by the activation of a stacked-foil target and subsequent gamma spectrometry. Theoretical cross sections were calculated up to 35 MeV with the EMPIRE nuclear reaction model code. The measured and calculated cross sections were used for deriving the thick-target yields and for estimating the production of other nuclides than {sup 177}Lu. Measured production cross sections ...

2009-11-15

6

Excitation functions for proton-induced reactions on natural hafnium: Production of "1"7"7Lu for medical use  

International Nuclear Information System (INIS)

There is an increasing interest in using radioisotopes of rare earth elements for internal radiotherapy and for imaging in nuclear medicine. "1"7"7Lu is one of the promising radionuclides. This article reports on the first measurements of the excitation function for the production of "1"7"7Lu with proton-beam energies up to 17 MeV on natural hafnium targets. The experimental cross sections for the reaction "n"a"tHf(p,x)"1"7"7Lu were obtained by the activation of a stacked-foil target and subsequent gamma spectrometry. Theoretical cross sections were calculated up to 35 MeV with the EMPIRE nuclear reaction model code. The measured and calculated cross sections were used for deriving the thick-target yields and for estimating the production of other nuclides than "1"7"7Lu. Measured production cross sections of "1"7"5","1"7"6","1"7"7","1"7"8Ta on the same target are also presented.

2009-11-01

7

Structure Of Multi-Quasiparticle Isomers In The Region Of 177Lu  

International Nuclear Information System (INIS)

High-K states in the region of 177Lu have been studied using multi-nucleon transfer reactions with 136Xe beams and Gammasphere. Results include identification of the predicted 5-quasiparticle K#pi# = 39/2 - isomer in 177Lu, a 7-quasiparticle K#pi# = 49/2 + isomer in 179Ta with an anomalously fast decay, and numerous other examples in a range of Yb close to stability. The results are discussed in the context of the expectations for multi-quasiparticle states near Z = 72 and the factors which may both govern isomer formation and also give an insight into K-purity, specifically chance degeneracies, and statistical mixing above the yrast line.

2005-04-05

8

In vitro and in vivo evaluation of novel ligands for radioimmunotherapy  

Energy Technology Data Exchange (ETDEWEB)

Novel ligands cis-2,6-bis[N,N-bis(carboxymethyl)aminomethyl]-1-piperidineacetic acid (PIP-DTPA), cis-[(1R,11S)-6,9,15-Tris-carboxymethyl-3,6,9,15-tetraazabicyclo[9.3.1] pentadec-3-yl]-acetic acid (PIP-DOTA), cis-{l_brace}2,7-bis-[bis-carboxymethyl-amino)-methyl]-azepan-1-yl{r_brace}-acetic acid (AZEP-DTPA), [2-(4,7-bis-carboxymethyl-[1,4,7]triazacyclononan-1-yl-ethyl] -2-carbonylmethyl-amino]-tetraacetic acid (NETA) and [{l_brace}4-carboxymethyl-7-[2-(carboxymethylamino)-ethyl]-perhydro-1,4,7-triazonin-1-yl{r_brace}-acetic acid (NPTA) are investigated as potential chelators of {sup 177}Lu, {sup 9}Y, {sup 212}Pb and {sup 213}Bi for radioimmunotherapy (RIT). The new ligands are radiolabeled with {sup 177}Lu, {sup 86/88/9}Y, {sup 203}Pb and {sup 205/6}Bi, and in vitro stability and in vivo stability of the radiolabeled complexes are assessed in human serum and athymic mice, respectively. In vitro studies ...

2006-05-15

9

Synergistic activity of the proteasome inhibitor PS-341 with non-myeloablative 153-Sm-EDTMP skeletally targeted radiotherapy in an orthotopic model of multiple myeloma  

UK PubMed Central (United Kingdom)

Multiple myeloma is a highly radiosensitive skeletal malignancy, but bone-seeking radionuclides have not yet found their place in disease management. We previously reported that the proteasome inhibitor...Full Text Available

2006-05-15

10

Tumour control probability (TCP) for non-uniform activity distribution in radionuclide therapy  

Energy Technology Data Exchange (ETDEWEB)

Non-uniform radionuclide distribution in tumours will lead to a non-uniform absorbed dose. The aim of this study was to investigate how tumour control probability (TCP) depends on the radionuclide distribution in the tumour, both macroscopically and at the subcellular level. The absorbed dose in the cell nuclei of tumours was calculated for {sup 90}Y, {sup 177}Lu, {sup 103m}Rh and {sup 211}At. The radionuclides were uniformly distributed within the subcellular compartment and they were uniformly, normally or log-normally distributed among the cells in the tumour. When all cells contain the same amount of activity, the cumulated activities required for TCP = 0.99 (A-tilde{sub TCP=0.99}) were 1.5-2 and 2-3 times higher when the activity was distributed on the cell membrane compared to in the cell nucleus for {sup 103m}Rh and {sup 211}At, respectively. TCP for {sup 90}Y was not affected by different radionuclide distributions, whereas for {sup ...

2008-08-21

11

Evaluation of Beta-Absorbed Fractions in a Mouse Model for 90Y, 188Re, 166Ho, 149Pm, 64Cu, and 177Lu Radionuclides  

Energy Technology Data Exchange (ETDEWEB)

Several short-lived, high-energy beta emitters are being proposed as the radionuclide components for molecular-targeted potential cancer therapeutic agents. The laboratory mice used to determine the efficacy of these new agents have organs that are relatively small compared to the ranges of these high-energy particles. The dosimetry model developed by Hui et al. was extended to provide realistic beta-dose estimates for organs in mice that received therapeutic radiopharmaceuticals containing 90Y, 188Re, 166Ho, 149Pm, 64Cu, and 177 Lu. Major organs in this model included the liver, spleen, kidneys, lungs, heart, stomach, small and large bowel, thyroid, pancreas, bone, marrow, carcass, and a 0.025-g tumor. The study as reported in this paper verifies their results for 90Y and extends them by using their organ geometry factors combined with newly calculated organ self-absorbed fractions from PEREGRINE and MCNP. PEREGRINE and MCNP agree to within 8% ...

2005-08-01

12

Preparation and dosimetry of radiotherapeutic particles for arthropaties; Preparacion y dosimetria de particulas radioterapeuticas para artropatias  

Energy Technology Data Exchange (ETDEWEB)

It was developed a new formulation of macro aggregates of Samarium 153 ({sup 153} Sm-MH) for the arthropaties treatment. The radio pharmaceutic was prepared by reaction of Samarium 153 chloride (SmCl{sub 3}) in aqueous environment with sodium boron hydride in NaOH 0.5 N. The microscopic analysis shown that the particles have an average size of 4% m (range 1-14 {mu} m). The velocity of sedimentation was 0.008 cm/min with high stability in vitro in human serum. The biological studies in healthy rabbits, shown that the complex is retained inside the articulation still eight days after of the administration of the radiopharmaceutical. Likewise, it is presented the data of absorbed dose in the different target organs, which was determined by thermoluminescent dosimetry (TLD) through the use of a REMCAL phantom (radiation equivalent manikin calibration). (Author)

1999-07-01

13

LLX separation of carrier-free {sup 47}Sc, {sup 48}V and {sup 48,49,51}Cr produced in {alpha}-particle activated titanium with HDEHP  

Energy Technology Data Exchange (ETDEWEB)

A LLX procedure for carrier-free separation of the radioisotopes, {sup 47}Sc, {sup 48}V and {sup 48},{sup 49},{sup 51}Cr, the 40 MeV {alpha}-particle activation products of titanium has been developed. Sequential separations of the radionuclides produced in the titanium matrix through the nuclear reactions ({alpha}, {alpha}p{chi}n), ({alpha}, p{chi}n) and {alpha}, ({chi}n) have been performed through LLX from aqueous H{sub 2}SO{sub 4} and HClO{sub 4} acid media using the liquid cation exchanger, HDEHP, as an extractant. Purity of the carrier-free radiotracers at different stages of their separations has been verified by {gamma}-ray spectrometry. (author).

1996-01-01

14

In vivo studies of the long-term "5"1Cr red cell survival of serologically incompatible red cell units  

International Nuclear Information System (INIS)

The long-term survival of serologically incompatible red cell units was measured in five patients with antibodies to high-frequency antigens. Initially, the survival of 1 ml of "5"1Cr-labeled incompatible red cells was measured over 1 hour. After demonstrating that the 1-hour survival times were successful (greater than 70%), each patient then received 5 ml of the same "5"1Cr-labeled red cells followed by the transfusion of the remainder of the red cell unit. The long-term T 1/2Cr survival for each case was patient 1 (anti-McCa), 15 days; patient 2 (anti-JMH), 12 days; patient 3 (anti-Kna), 31 days; patient 4 (anti-McCa), 12 days; and patient 5 (anti-Hya), 14 days. Each antibody tested in an in vitro homologous macrophage assay showed less than 5 percent phagocytosis. Anti-JMH was the only antibody to react with IgG subclass antisera and was determined to be IgG4. The macrophage assay, IgG subclass testing, and short-term (1 hour, 1 ml) "5"1Cr survival studies all indicated that the ...

15

Measurement and analysis of neutron production cross sections and determination of some reaction rates for nuclear astrophysical calculations  

International Nuclear Information System (INIS)

The absolute cross sections of "2"3Na(p,n)"2"3Mg, "2"7Al(p,n)"2"7Si and "3"0Si(#alpha#,n)"3"3S reactions were measured in the incident energy range of 5.05 to 5.80, 5.80 to 6.25 and 3.975 to 6.235 MeV respectively using a spherically shaped 4#pi# neutron detector. In the energy range 5.80 to 7.80 and 6.235 to 11.30 MeV the absolute cross sections of "2"3Na(p,n)"2"3Mg and "3"0Si-(#alpha#,n)"3"3S reactions were determined by optical model calculations. The cross sections of the inverse reactions "2"3Mg(n,p)"2"3Na and "3"3S(n,#alpha#)"3"0Si were also calculated by the same method for the neutron energy range of 10 keV to 7.50 MeV for each reaction. The cross section of the latter reaction in the neutron energy range of 10 keV to 840 keV was also determined from its inverse reaction "3"0Si(#alpha#,n)"3"3S by the application of the detailed balance theorem. The reactions for which the cross sections were determined are of importance in stellar evolution and nucleosynthesis in stars. The ...

16

Precise radiometry: Some recent aspects of fruitful interaction with atomic physics  

International Nuclear Information System (INIS)

Modern radiometric analytics demands a complex consideration of nuclear and electron shell processes, if more pretentious aims are envisaged. As an example the small variation of decay rates of radionuclides presents possibilities for information on chemical situations of decaying atoms. In principle this phenomenon is well known since many years, but now the situation is such that, e.g. in /sup 99m/Tc internal conversion, a full agreement of the difficult experiments and the respective theory was established. The secondary emission of X-rays as a consequence of high excitation of electron shells in combination with nuclear transitions supplies another example for a methodical progress of radiometry. Investigations on "5"1Cr as an electron capture nuclide have shown that chemically induced variations of the K/sub #alpha#/ to K/sub #beta#/ X-ray intensity ratio is at least qualitatively understood. (author).

1986-01-01

17

Radionuclide adsorption characteristics around coastal water  

Energy Technology Data Exchange (ETDEWEB)

The adsorption capacity of radionuclides onto suspended sediment was experimented on each of the coastal seawater sampled around the Kori and the Wolsung nuclear power plant. During the experiment the quantity and size fraction of suspended sediment were adjusted and the seawater and sediment chemistry is approximated to the expected field condition. Because the sorption capacity depends on the specific minerals, ocean chemistry and radionuclide involved, it is necessary to analyze sediment mineralogy. Clay mineral is dominant in seabed mineral and suspended sediment as the result of x-ray diffraction. Radionuclide sorbed to silty-clay mineral can be rather transported to ocean than scavenged to seabed because of low quantity and fine grained suspended sediment in the coast around the Kori and the Wolsung. The result of adsorption examinations shows that {sup 139}Ce and {sup 51}Cr and {sup 110m}Ag are strongly sorbed to suspended particle, ...

1999-07-01

18

Radionuclide adsorption characteristics around coastal water  

International Nuclear Information System (INIS)

The adsorption capacity of radionuclides onto suspended sediment was experimented on each of the coastal seawater sampled around the Kori and the Wolsung nuclear power plant. During the experiment the quantity and size fraction of suspended sediment were adjusted and the seawater and sediment chemistry is approximated to the expected field condition. Because the sorption capacity depends on the specific minerals, ocean chemistry and radionuclide involved, it is necessary to analyze sediment mineralogy. Clay mineral is dominant in seabed mineral and suspended sediment as the result of x-ray diffraction. Radionuclide sorbed to silty-clay mineral can be rather transported to ocean than scavenged to seabed because of low quantity and fine grained suspended sediment in the coast around the Kori and the Wolsung. The result of adsorption examinations shows that "1"3"9Ce and "5"1Cr and "1"1"0"mAg are strongly sorbed to suspended particle, while "1"3"7Cs is less sorbed and "6"0Co uptake is ...

1999-11-04

19

Purification of radioactive decontamination liquids from NPP Paks with reactive adsorption and ion-exchange process  

International Nuclear Information System (INIS)

In nuclear power plant Paks, Hungary, alkaline oxidative (NaOH, KMnO_4, H_2O) and acidic reductive (citric- and oxalic acid, water) liquids are using for the decontamination of primary circuit equipment (main liquid circulating pumps, steam generators, pipelines etc). The above mentioned decontamination liquids are containing "1"1"0"mAg, "9"5Nb, "5"4Mn, "5"8 Co, "6"0Co, "5"1 Cr, "1"2"4 Sb radioisotopes, summarized radioactivity is between 10"3-8x10"4 kBq/dm"3 liquid. The decontamination liquid can be cleaned with reactive adsorption (active carbon) and ion-exchange process at elevated temperature (333-368 K) in multilayered columns. After purification the summarized radioactivity for "5"4Mn, "6"0Co, and "1"1"0"mAg are in the outlet liquid below 1 kBq/dm"3. Decontamination factor DF#approx =#10"3-10"4, volumetric reduction factor VRF#approx =#50-500.

1999-11-04

20

Measurement of relative K X-ray intensity ratio following radioactive decay and photoionization  

Energy Technology Data Exchange (ETDEWEB)

The measurements of the K X-ray intensity ratio I(K{alpha} {sub 2}/K{alpha} {sub 1}), I(K{beta} {sub 1}/K{alpha} {sub 1}) and I(K{beta}/K{alpha}) for elements V, Mn, Zn, Tc, Ru, Cd, Xe, Ba, Cs, Hg and Rn were experimentally determined both by photon excitation, in which 59.5 keV {gamma}-rays from a {sup 241}Am and 123.6 keV {gamma}-rays from a {sup 60}Co were used, and following the radioactive decay of {sup 51}Cr, {sup 55}Fe, {sup 67}Ga, {sup 99}Tc, {sup 111}In, {sup 131}I, {sup 133}Ba, {sup 133}Xe, {sup 137}Cs, {sup 201}Tl and {sup 226}Ra. K X-rays emitted by samples were counted by a Si(Li) detector with resolution 160 eV at 5.9 keV. Obtained values were compared with the theoretical values. It was observed that present values agree with the previous theoretical and other experimental results.

2007-01-15

 
 
 
 
21

Measurement of relative K X-ray intensity ratio following radioactive decay and photoionization  

International Nuclear Information System (INIS)

The measurements of the K X-ray intensity ratio I(K#alpha# _2/K#alpha# _1), I(K#beta# _1/K#alpha# _1) and I(K#beta#/K#alpha#) for elements V, Mn, Zn, Tc, Ru, Cd, Xe, Ba, Cs, Hg and Rn were experimentally determined both by photon excitation, in which 59.5 keV #gamma#-rays from a "2"4"1Am and 123.6 keV #gamma#-rays from a "6"0Co were used, and following the radioactive decay of "5"1Cr, "5"5Fe, "6"7Ga, "9"9Tc, "1"1"1In, "1"3"1I, "1"3"3Ba, "1"3"3Xe, "1"3"7Cs, "2"0"1Tl and "2"2"6Ra. K X-rays emitted by samples were counted by a Si(Li) detector with resolution 160 eV at 5.9 keV. Obtained values were compared with the theoretical values. It was observed that present values agree with the previous theoretical and other experimental results.

2007-01-01

22

Preliminary activation calculations for the PDX tokamak  

Energy Technology Data Exchange (ETDEWEB)

Activation dose rates have been computed for the Poloidal Divertor Experiment Tokamak at the Princeton Plasma Physics Laboratory. Dose rates were computed in one-dimensional (cylindrical) geometry using the ANISN S/sub n/ transport theory code and the DKR radioactivity code. The EPR (DLC37F) 121-group coupled neutron-gamma cross section library was used with ANISN. For DKR, the 46-group neutron library of DCDLIB was employed. Dose rates were calculated for 1 minute, 1 hour, 6 hours, 24 hours, 1 week, and 1 month following a single pulse yielding 10/sup 15/ neutrons and for 2 hypothetical pulsing sequences. First, it was assumed that 10 pulses were conducted each day (1 hour apart) for 5 days. Second, it was assumed that 100 pulses were conducted each day (6 minutes apart) for 5 days. It was found that /sup 56/Mn and /sup 64/Cu are the main contributors to the dose at short time periods after shutdown, while, for long time periods, /sup 58/Co and /sup ...

1980-10-01

23

Cellular dosimetry: Absorbed fractions for monoenergetic electron and alpha particle sources and S-values for radionuclides uniformly distributed in different cell compartments  

Energy Technology Data Exchange (ETDEWEB)

The importance of cellular dosimetry in both diagnostic and therapeutic nuclear medicine is becoming increasingly recognized. Experimental range-energy relations for electrons and alpha particles, along with derived geometric reduction factors, are used to calculate cellular absorbed fractions for these radiations. The resulting absorbed fractions are employed to calculate cellular S-values for several radionuclides. Cellular absorbed fractions for monoenergetic electron sources with energies ranging from 0.1 keV to 1 MeV, distributed uniformly in the source region, are calculated for several target {l_arrow} source combinations including cell{l_arrow}cell, cell{l_arrow}cell surface, nucleus{l_arrow}nucleus, nucleus {l_arrow}cytoplasm and nucleus {l_arrow}cell surface. Similar data are also provided for monoenergetic alpha particle sources with energies ranging from 3 to 10 MeV. S-values are also conveniently tabulated for {sup 32}P, {sup 35}S, {sup 86}Rb, {sup 89}Sr, {sup 90}Y, {sup ...

1994-02-01

24

Activation analysis of trace elements in titanium-molybdate target used for pre-formed TiMo gel based "9"9"mTc generator production and radionuclidic impurity of "9"9"mTc pertechnetate eluate  

International Nuclear Information System (INIS)

A gel-type "9"9Mo-"9"9"mTc generator using Titanium-Molybdate target (TiMo-target) as column packing was developed in Radioisotope Department, the Dalat Nuclear Research Institute [1]. The concentration of trace elements in TiMo-target and radionuclidic purity in "9"9"mTc solution eluted from this type of generator were studied for quality control purpose. The monostandard method in neutron activation analysis has been applied to determine the concentration of trace impurities in titanium-molybdate target. For neutron activation analysis, TiMo samples were irradiated in the different channels of nuclear reactor IVV-9 at a neutron flux of maximum 2.1 x 10"1"3 n.cm"-"2s"-"1. The following chemical element impurities were determined: Na, W, Co, Fe, Zn, Ag, Sb and Cr. The gamma ray emitted nuclides found in "9"9"mTc solution eluted from our "9"9"mTc generator were the following: "6"5Zn, "6"0Co, "1"1"0"mAg, "5"9Fe, "5"1Cr, "2"4Na, "8"2Br and "9"9Mo. "9"9Mo was found less than 2.10"-"6mCi ...

2004-06-01

25

ZZ MCB-JEF2.2, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K  

International Nuclear Information System (INIS)

1 - Description of program or function: MCB-JEF2.2 is a continuous-energy cross section libraries in ACE Format suitable for the MCB-1C and MCNP codes. Libraries for various materials were generated at six different Temperatures, and cover the energy range up to 20 MeV. Format: ACE. Number of groups: Continuous energy. Nuclides: H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat., N-14, N-15, O-16, O-17, Na-23, F-19, Mg-nat., Al-27, Si-nat., P-31, S-32, S-33, S-34, S-36, Cl-nat, K-nat, Ca-nat., Ti-nat, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-59, Ni-60, Ni-61, Ni-62, Ni-64, Cu-nat, Ga-nat, Ge-72, Ge-73, Ge-74, Ge-76, As-75, Se-74, Se-76, Se-77, Se-78, Se-80, Se-82, Br-79, Br-81, Kr-78, Kr-80, Kr-82, Kr-83, Kr-84, Kr-85, Kr-86, Rb-85, Rb-86, Rb-87, Sr-84, Sr-86, Sr-87, Sr-88, Sr-89, Sr-90, Y-89, Y-90, Y-91, Zr-nat, Zr-90, Zr-91, Zr-92, Zr-93, Zr-94, Zr-95, Zr-96, Nb-93, Nb-94, Nb-95, Mo-nat, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, ...