Preparation of carrier-free 47Sc by chemical separation from 47Ca and its distribution in tumor bearing mice

Hara, Toshihiko; Freed, Barry R.

doi:10.1016/0020-708x(73)90016-1

Cited by 13 publications

(10 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Several investigations have been performed with mice and rats regarding organ distribution after intravenous administration of Sc3+ (281)(282)(283)(284). The results compare well and show that the chemical form used for the administration is of great importance (284).…”

Section: Metabolism and Effects Of Similar Ionsmentioning

confidence: 80%

“…10. Shown for Ga3+ in humans (214,237) and rats (238), for Sc3+ in mice (282), for Y3+ in rabbits (292,295), for Be" in cows (312), for Zr4+ in rabbits (292), and for Cr3+ in rats (402,403).…”

Section: Discussionmentioning

confidence: 99%

“…Initially, the concentration is high in the lungs and kidneys. After 3 to 24 hr it is highest in the liver and spleen (283), and after 72 hr highest in the skeleton, but still high in the reticuloendothelial system (282). After 11 months, the concentration is highest in the spleen and bone marrow and appears to have diminished in the liver and skeleton (281).…”

Section: Metabolism and Effects Of Similar Ionsmentioning

confidence: 97%

See 2 more Smart Citations

Metabolism and possible health effects of aluminum.

Ganrot¹

1986

Environ Health Perspect

203

150

View full text Add to dashboard Cite

Literature regarding the biochemistry of aluminum and eight similar ions is reviewed. Close and hitherto unknown similarities were found. A hypothetical model is presented for the metabolism, based on documented direct observations of Al3+ and analogies from other ions. Main characteristics are low intestinal absorption, rapid urinary excretion, and slow tissue uptake, mostly in skeleton and reticuloendothelial cells. Intracellular Al3+ is probably first confined in the lysosomes but then slowly accumulates in the cell nucleus and chromatin. Large, long-lived cells, e.g., neurons, may be the most liable to this accumulation. In heterochromatin, Al3+ levels can be found comparable to those used in leather tannage. It is proposed that an accumulation may take place at a subcellular level without any significant increase in the corresponding tissue concentration. The possible effects of this accumulation are discussed. As Al3+ is neurotoxic, the brain metabolism is most interesting. The normal and the lethally toxic brain levels of Al3+ are well documented and differ only by a factor of 3-10. The normal brain uptake of Al3+ is estimated from data on intestinal uptake of Al3+ and brain uptake of radionuclides of similar ions administered intravenously. The uptake is very slow, 1 mg in 36 years, and is consistent with an assumption that Al3+ taken up by the brain cannot be eliminated and is therefore accumulated. The possibility that Al3+ may cause or contribute to some specific diseases, most of them related to aging, is discussed with the proposed metabolic picture in mind.

show abstract

Section: Metabolism and Effects Of Similar Ionsmentioning

confidence: 80%

Section: Discussionmentioning

confidence: 99%

Section: Metabolism and Effects Of Similar Ionsmentioning

confidence: 97%

See 1 more Smart Citation

Metabolism and possible health effects of aluminum.

Ganrot¹

1986

Environ Health Perspect

203

150

View full text Add to dashboard Cite

show abstract

“…Good summaries of those methods have been given [49,50]. Similarly, separation methods of 47 Sc from an irradiated Ca target have also been described [55][56][57][58].…”

Section: Production Of 47 Scmentioning

confidence: 99%

New developments in the production of theranostic pairs of radionuclides

Qaim

Schölten

Neumaier

2018

J Radioanal Nucl Chem

132

View full text Add to dashboard Cite

A brief historical background of the development of the theranostic approach in nuclear medicine is given and seven theranostic pairs of radionuclides, namely 44g Sc/ 47 Sc, 64 Cu/ 67 Cu, 83 Sr/ 90 Sr, 86 Y/ 90 Y, 124 I/ 131 I, 152 Tb/ 161 Tb and 152 Tb/ 149 Tb, are considered. The first six pairs consist of a positron and a β −-emitter whereas the seventh pair consists of a positron and an α-particle emitter. The decay properties of all those radionuclides are briefly mentioned and their production methodologies are discussed. The positron emitters 64 Cu, 86 Y and 124 I are commonly produced in sufficient quantities via the (p,n) reaction on the respective highly enriched target isotope. A clinical scale production of the positron emitter 44g Sc has been achieved via the generator route as well as via the (p,n) reaction, but further development work is necessary. The positron emitters 83 Sr and 152 Tb are under development. Among the therapeutic radionuclides, 89 Sr, 90 Y and 131 I are commercially available and 161 Tb can also be produced in sufficient quantity at a nuclear reactor. Great efforts are presently underway to produce 47 Sc and 67 Cu via neutron, photon and charged particle induced reactions. The radionuclide 149 Tb is unique because it is an α-particle emitter. The present method of production of 152 Tb and 149 Tb involves the use of the spallation process in combination with an on-line mass separator. The role of some emerging irradiation facilities in the production of special radionuclides is discussed.

show abstract

“…The spleen is added to the generic model structure because human and animal data indicate that it is an important repository for scandium. The generic structure is also modified with regard to routes of transfer to and from the marrow compartments, based on indications from animal studies of relatively high transfer of scandium from plasma to marrow (Rosoff et al., 1963, 1965; Hara and Freed, 1973; Byrd et al., 1975; Lachine et al., 1976). (249) Transfer coefficients in the characteristic model for scandium are set for consistency with the following data: (1) for human subjects, measurements of blood clearance over 3 d, urinary and faecal excretion rates over 15 d, whole-body retention over 1.5 y, and activity concentrations in autopsy tissues of subjects dying 5–7 months after injection (Rosoff et al., 1965); and (2) measurements of the time-dependent systemic distribution of activity in rats, mice, and rabbits (Durbin, 1960; Rosoff et al., 1963; Basse-Cathalinat et al., 1968; Hara and Freed, 1973; Byrd et al., 1975; Lachine et al., 1976).…”

Section: Calcium (Z = 20)mentioning

confidence: 99%

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

Paquet¹,

Bailey²,

Leggett³

et al. 2016

Ann ICRP

View full text Add to dashboard Cite

The 2007 Recommendations of the International Commission on Radiological Protection (ICRP, 2007) introduced changes that affect the calculation of effective dose, and implied a revision of the dose coefficients for internal exposure, published previously in the Publication 30 series (ICRP, 1979, 1980, 1981, 1988b) and Publication 68 (ICRP, 1994b). In addition, new data are available that support an update of the radionuclide-specific information given in Publications 54 and 78 (ICRP, 1988a, 1997b) for the design of monitoring programmes and retrospective assessment of occupational internal doses. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data was performed by Committee 2, Task Group 21 on Internal Dosimetry, and Task Group 4 on Dose Calculations. A new series, the Occupational Intakes of Radionuclides (OIR) series, will replace the Publication 30 series and Publications 54, 68, and 78. Part 1 of the OIR series has been issued (ICRP, 2015), and describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment. The following publications in the OIR series (Parts 2–5) will provide data on individual elements and their radioisotopes, including information on chemical forms encountered in the workplace; a list of principal radioisotopes and their physical half-lives and decay modes; the parameter values of the reference biokinetic model; and data on monitoring techniques for the radioisotopes encountered most commonly in workplaces. Reviews of data on inhalation, ingestion, and systemic biokinetics are also provided for most of the elements. Dosimetric data provided in the printed publications of the OIR series include tables of committed effective dose per intake (Sv per Bq intake) for inhalation and ingestion, tables of committed effective dose per content (Sv per Bq measurement) for inhalation, and graphs of retention and excretion data per Bq intake for inhalation. These data are provided for all absorption types and for the most common isotope(s) of each element. The electronic annex that accompanies the OIR series of reports contains a comprehensive set of committed effective and equivalent dose coefficients, committed effective dose per content functions, and reference bioassay functions. Data are provided for inhalation, ingestion, and direct input to blood. The present publication provides the above data for the following elements: hydrogen (H), carbon (C), phosphorus (P), sulphur (S), calcium (Ca), iron (Fe), cobalt (Co), zinc (Zn), strontium (Sr), yttrium (Y), zirconium (Zr), niobium (Nb), molybdenum (Mo), and technetium (Tc).

show abstract

Preparation of carrier-free 47Sc by chemical separation from 47Ca and its distribution in tumor bearing mice

Cited by 13 publications

References 7 publications

Metabolism and possible health effects of aluminum.

Metabolism and possible health effects of aluminum.

New developments in the production of theranostic pairs of radionuclides

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

Contact Info

Product

Resources

About