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Volume 38, Issue 5
Displaying 1-8 of 8 articles from this issue
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Tomiyasu ITO, Norio NOGAWA, Kunio OOHASHI, Asao NAKAMURA, Naotake MORI ...1989 Volume 38 Issue 5 Pages 237-243
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSFor the purpose of searching some effective absorbents of gaseous radioactive iodine, 16 substances considered as having an affinity for iodine were investigated with regular iodine and 125I. In a preliminary survey, only tetrathiafulvalene (TTF) was found to have satisfactory absorbing properties comparable to activated charcoal. A further detailed comparison of the properties between TTF and activated charcoal led us to the conclusion that the former has more preferable properties as absorbent of radioactive iodine than the latter in all points studied. The results are summarized as follows:
(1) The absorption of iodine on TTF in atmosphere was about twice as much as that on activated charcoal. Desorption of iodine from saturatedly absorbed iodine on TTF was practically negligible except trace amount of initial desorption, while that on activated charcoal was considerable (3%/50 h) even in the air at room temperature.
(2) Absorbed amount of iodine on activated charcoal decreased with increasing gaseous iodine concentration, air flow rate, or humidity of flowing-air. On the other hand, those factors scarcely affected that on TTF. Under an air flow rate of 1 m/s, activated charcoal absorbs only 80% of iodine, while TTF absorbs more than 99%.
(3) In flowing-air saturated with water vapor, iodine absorbed on activated charcoal was gradually liberated although by small amount (0.08%/100 h), while that on TTF was much more stable for a long period (0.004%/100 h) .
As a conclusion, TTF is considered to be useful as a quite effective radioactive iodine absorbent, especially in the case where protection from radioactive iodine should be serious, though it is expensive now.View full abstractDownload PDF (781K) -
Hiyoshimaru OYAMADA, Susumu YAMAZAKI, Masatoshi MAKUUCHI, Hiroshi HASE ...1989 Volume 38 Issue 5 Pages 244-251
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSHepatobiliary scintigraphy with 99mTc-N-pyridoxyl-5-methyltryptophan (99mTe-PMT ) was carried out on 48 patients with intrahepatic masses, 44 with hepatocellular carcinoma and one each of hepatocellular adenoma, focal nodular hyperplasia, cholangiocellular carcinoma, and adenoid cystic carcinoma. Scans were performed twice, early scan (30 min post i.v.) and delayed scan (2.5 h post i.v.), and the delayed scan was used for assessing the accumulation of 99mTc-PMT in the intrahepatic masses.
In the hepatocellular carcinoma group, based on individual patients, 17 out of 44 (38.6%) showed accumulation of 99mTc-PMT in various degrees; and based on individual masses, accumulation was noted in 21 out of 55 masses (38.2%) . However, only the cases which had not received transarterial infusion of anti-cancer drugs (TAI) and/or-blocking agents (TAE) were taken into consideration, 9 out of 18 patients (50%) and 12 out of 25 masses (48.0%) were found capable of picking up 99mTc-PMT. A case of hepatocellular adenoma showed a strong accumulation of 99mTc-PMT in the mass which was depicted as a defect on the 99mTc-colloid scan and did not show a significant accumulation of 67Ga. In a case of focal nodular hyperplasia, there were two space-occupying lesions (SOLs) , one of which showed a clear-cut defect on the 99mTc-colloid scan and the other which showed only a distorted uptake pattern. However, both masses were strongly positive with 99mTc-PMT.
99mTc-PMT scintigraphy is useful in connection with 99mTc-colloid scan and sometimes with 67Ga-citrate in the diagnosis of intrahepatic masses originating from hepatocytes.View full abstractDownload PDF (5269K) -
Hiroshi MIYAHARA, Yasunori NOZUE, Tamaki WATANABE1989 Volume 38 Issue 5 Pages 252-254
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSA live-timed bi-dimensional data acquisition system was applied for standardization of 152Eu by 4 πβ-γ spectroscopic coincidence counting that was proposed by Baba et al. [Nucl. Instr. Meth., 203, 273 (1982) ] . A 4 πβ pressurized proportional counter detects β- particles, Auger electrons and X-rays, and a high purity germanium detector measures γ rays. Digitized data from both detectors on coincidences and anti-coincidences are stored on magnetic tapes. A micro computer extracts the single γ spectrum and the γ spectrum coincident with the β pulses from them, and activity of 152Eu is calculated from both spectra by the 4 πβ-γ spec-troscopic coincidence method. This apparatus not only decrease a half of measurement time but also the statistical uncertainty is largely improved. Furthermore, it is effective that the detection efficiencies unknown for β- rays are estimated using mass absorption coefficients.View full abstractDownload PDF (349K) -
Tohru ADACHI, Akira TANAKA, Tsutomu YAMAHA1989 Volume 38 Issue 5 Pages 255-258
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSAbsorption, distribution, metabolism and excretion were studied in rats following a single oral administration of N-cyclohexyl-2-benzothiazyl sulfenamide (CBS) at a dose of 250 mg/kg. About 65% and 24% of the dose were excreted into urine and feces, respectively, for 3 days after administration of labeled CBS (cyclohexyl-14C) Biliary excretion amounted to about 5 % of the dose for 3 days. While about 92% of the dose was recovered in urine and feces at a ratio of 1: 1 within 3 days when 14C-2CBS was given.
No specific organ-affinity was observed in distribution study. Cyclohexylamine and 2-mer-captobenzothiazole were identified as urinary metabolites.View full abstractDownload PDF (485K) -
Takahisa KATO, Kazumi SAITO, Norio KURIHARA1989 Volume 38 Issue 5 Pages 259-262
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSWe tested the performance of “Ready Cap” which can be used in place of liquid scintillation cocktails to measure the activity of 3H and 14C with a liquid scintillation counter, and observed satisfactory results on counting efficiencies for these nuclides. We could correct color-quenching with Ready Cap either by a method of the gravity-center of β-ray spectrum or by an external standard method that uses the external irradiation from bottom of the sample. Although there are several problems such as limitation of the maximum sample volumes (<200 μl) and sample preparation procedures (drying the sample solution), we can conveniently employ Ready Cap in some aspects of activity counting because of the easy disposal procedure of the radioactive waste resulting from it.View full abstractDownload PDF (486K) -
Kazuhiro SHIBA, Hirofumi MORI, Kinichi HISADA1989 Volume 38 Issue 5 Pages 263-266
Published: May 15, 1989
Released on J-STAGE: September 07, 2010
JOURNAL FREE ACCESSWe carried out the efficiency test of Ready Cap, a solvent free scintillation material, using a non-volatile 3H-labeled compound and a liquid scintillation counter (Aloka LSC-1000) . The following results were obtained:
(1) The tritium efficiency was about 40% and varied narrowly.
(2) Potential sample volume for high efficiency was up to 200 μl.
(3) Significant decrease in the counting efficiency was caused by incomplete drying and the presence of non-volatile solutes such as high molarity buffers.
(4) Chemiluminescence was not observed.
(5) Color quenching correction except high quenching level was successfully made by SCCR method.
Thus, it is suggested that Ready Cap might be convenient for measurement of counting rate, althongh this method is limited in quantitative estimation of radioactivity.View full abstractDownload PDF (526K) -
Nagao IKEDA1989 Volume 38 Issue 5 Pages 267-268
Published: May 15, 1989
Released on J-STAGE: July 21, 2010
JOURNAL FREE ACCESSDownload PDF (202K) -
1989 Volume 38 Issue 5 Pages A33P-A50M
Published: May 15, 1989
Released on J-STAGE: July 21, 2010
JOURNAL FREE ACCESSDownload PDF (3415K)
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