RADIOISOTOPES

Isotopic Fractionation of Fentanyl and Its Deuterated Analogues by Capillary Gas Chromatography

Shoji SERA, Tsuyoshi GOROMARU

1997Volume 46Issue 12 Pages 885-892
Published: December 15, 1997
Released on J-STAGE: September 07, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_885

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Isotopic fractionation of fentanyl (FT) and its deuterated analogues by gas chromatography using capillary columns (CBP1 and CBP5) has been investigated. Seven kinds of analogues were labeled with 5 to 19 deuterium atoms at the anilino, propionyl and/or phenylethyl group of FT. The retention times of deuterated FT in CBP1 and CBP5 columns are inversely proportional to the number of labeled deuterium atoms in the molecule. The difference in free energy changes (ΔΔG) had a linear relationship with the number of labeled deuterium atoms, except for labeling at anilino and phenylethyl group. The contribution of a deuterium atom to the ΔΔG value was estimated to be 1.13 cal/mol in CBP1 and 1.40 cal/mol in CBP5, respectively. While, its contribution in the propiony group was 2.84 cal/mol in CBP1 and 2.48 cal/mol in CBP5, respectively. An important factor in separation by GC may differences in interactions between the stationary phase of the column with the three dimensional protrusive moiety in the molecule.

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Intensive Study for Behavior of ³H, ¹⁴C, ³²P, ³⁵S, and ⁴⁵Ca during the Incineration of Liquid Scintillation Cocktail Waste

Norio NOGAWA, Katuji MATUOKA, Yoshihiro MAKIDE, Naotake MORIKAWA

1997Volume 46Issue 12 Pages 893-903
Published: December 15, 1997
Released on J-STAGE: September 07, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_893

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Liquid scintillation counters are widely used for the assay of β^- ray emitting radioisotopes. In Japan it is mandatory for liquid scintillation cocktail waste containing 5 nuclides (³H, ¹⁴C, ³²P, ³⁵S, ⁴⁵Ca) to be incinerated by a specially designed incineration system. We examined the performance of incineration systems and beheavior of radioisotopes during incineration from the viewpoints of safe handling of radioisotopes and environmental protection.
Size distribution of radioactive particles in the exhaust air was studied. ₃H and ¹⁴C were not observed because they produce gaseous chemical compounds during incineration. ³²P, ³⁵S and ⁴⁵Ca particles were less than 1μm, between 0.1 and 1μm (U-shape distribution with minimum at 0.3-0.6 μm), and between 0.1 and 3μm (with maximum at 1 μm), respectively.
Translocation percentages of ³H, ¹⁴C, ³²P, ³⁵S, and ⁴⁵Ca to the exhaust air and cooled washing water (exhaust water) were about 2.2, 94, 27, 5.6, 33 and 96, 1.3, 35, 76, 34%. pH values of the cooled washing water were about 5.5 and 7 under the normal incineration conditions and at the end of incineration, respectively. Chemical oxygen demand (COD) and insoluble substance concentrations in the exhaust water after incineration were less than 3 ppm and less than 5 mg/L, respectively. Trapping efficiency of the filter unit constructed with prefilters and HEPA filters for ³²P, ³⁵S and ⁴⁵Ca particles were 99.95±0.02, 99.62±0.27, and 99.97±0.01%, respectively.

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Estimation of the Absorbed Dose to Mice in Prolonged Irradiation by Low-Dose Rate γ-Rays from ¹³⁷Cs Sources

Akihiro SHIRAGAI, Mikio SAITOU, Iwao KUDO, Shoko KANAIWA-KUDO, Tsuneya ...

1997Volume 46Issue 12 Pages 904-911
Published: December 15, 1997
Released on J-STAGE: September 07, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_904

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A prolonged irradiation facility to study late effects on mice by continuous γ-ray irradiation at low-dose rates was established at the Institute for Environmental Sciences (IES), Aomori prefecture, Japan. Before starting studies of late effects, the absorbed doses to mice were estimated in detail. Three ¹³⁷Cs γ-sources were individually used to expose mice in three irradiation rooms. The cages for mice were arranged so that the mean absorbed doses in the abdomen of a mouse would reach 8000, 400, 20mGy by exposures for about 400 days in respective rooms. The positions of the cages on the shelves of racks were presumed by using two air-ionization chambers whose ionization volume were about 12 and 1200 ml, respectively. Furthermore, by inserting TLD phosphors into the abdomens of mice, the absorbed doses were directly obtained under the actual exposure conditions.
The absorbed dose distributions in air at the source level above the floor never showed an inverse-square law behavior with the distance from the source, and also never showed geometric symmetry in every irradiation room. Except for errors concerning the positions of the racks and cages, the uncertainties in the exposure doses were estimated to be about ±12% for a 8000 mGy group, 17% for a 400 mGy group and 35% for a 20 mGy group.

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Radioluminographic Monitoring of Radioactive Surface Contamination on a Rough Surface Material

Etsuko FURUTA, Yukio YOSHIZAWA, Takashi NATAKE, Makoto TAKIUE

1997Volume 46Issue 12 Pages 912-916
Published: December 15, 1997
Released on J-STAGE: September 07, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_912

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Floating radioluminography using an imaging plate can be sufficiently applied to the monitoring of the surface contamination on rough surface materials at a radioisotope facility. This technique is superior to the smear method which has been used to estimate the contamination of low energy β-ray emitters, because the fixed contamination and the contamination on the coarse surface materials have been difficult to be wiped out on a smear paper. The radiation detection efficiency of the imaging plate is as high as the liquid scintillation technique, when the plate is exposed with the sample in a vacuum chamber. In this study, the technique has been tested to the surface monitoring of a liquid-waste concrete cistern, and the sort of contaminant radioisotope was estimated by inserting a plastic film or an aluminum plate between the imaging plate and the sample.

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Reliability of Individual Doses Relating to the Epidemiological Studies on Nuclear Industry Workers in Japan (2)

Changes of Technology on Radiation Measurement, Coordination of Measured Doses, Addition of Doses and Quality Assurance

Epidemiological Study Group on Evaluation of

1997Volume 46Issue 12 Pages 917-932
Published: December 15, 1997
Released on J-STAGE: July 21, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_917

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Recent Aspects of Radiation Sterilization

3. Crude Drugs·Chinese Herbal (Medicines)

Syojiro KIMURA

1997Volume 46Issue 12 Pages 933-941
Published: December 15, 1997
Released on J-STAGE: July 21, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_933

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[title in Japanese]

[in Japanese]

1997Volume 46Issue 12 Pages 943-944
Published: December 15, 1997
Released on J-STAGE: July 21, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_943

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[title in Japanese]

[in Japanese]

1997Volume 46Issue 12 Pages 945-946
Published: December 15, 1997
Released on J-STAGE: July 21, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_945

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[title in Japanese]

[in Japanese]

1997Volume 46Issue 12 Pages 947-948
Published: December 15, 1997
Released on J-STAGE: July 21, 2010

DOIhttps://doi.org/10.3769/radioisotopes.46.12_947

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