Thyroid Dose Estimation Using WBC and I-131 Concentration in Working Area of Radioisotope Production at Normal Operation; Perkiraan Dosis Thyroid Melalui Pengukuran WBC dan Perhitungan dengan Konsentrasi I-131 Di Daerah Kerja Pada Operasi Normal Produksi Radioisotop

Energy Technology Data Exchange (ETDEWEB)

Tedjasari, R S; Lubis, E [Radioactive-Waste Management Technology Centre, National Atomic Energy Agency of Indonesia(Indonesia)

1996-07-01

Thyroid dose estimation at Radioisotope Production Centre workers using WBC and calculation based on I-131 concentration in working area has been done. The aim of this research is to get the relation between WBC result and calculation using I-131 concentration in working area. The result indicates differences in a range of 3,2% to 53,2%. These differences caused of parameters which influence the calculation are not accurate. These results also indicate that dose estimation using WBC is relatively batter and more accurate but need to have certain information about time of intake.

Therapeutical uses of 131I

International Nuclear Information System (INIS)

Lago, Graciela.

1994-01-01

Physiology of thyroid gland, pathology of thyroid , papillary, follicular cancer is considered together as differentiated thyroid cancer with very good results under therapy with iodine, invitro determination of calcitonin, search of metastasis, anaplastic carcinoma, as indifferentiated carcinoma with similar results as medullary carcinoma. This work gives a protocol for therapeutical use of 131I , in hyperthyroidism due to Graves-Basedow disease, thyrotoxic adenoma or Plummer disease, toxic multi nodular goiter, subacute thyroiditis. Is studied too the treatment with pharmaceuticals, surgery and radioactive iodine. A recommended use of each and protocol for iodine administration, fixed dose technique, dose estimation,absorbed dose, recommendations about when to use and not use 131I are included in this work

Medical and Other Radioisotopes as Tracers in the Wastewater-River-Sediment Chain

Energy Technology Data Exchange (ETDEWEB)

Fischer, H. W.; Ulbrich, S.; Pittauerova, D.; Hettwig, B. [Institute of Environmental Physics, University of Bremen, Bremen (Germany)

2013-07-15

Medical, natural and other artificial radioisotopes have been followed on their pathway to river sediment employing gamma spectroscopy. Sampling points were situated at a local wastewater treatment plant (inflow, outflow and sludge) and along 70 km of a tidal river (bank sediment). Isotope entry points are assumed to be wastewater for medical isotopes like I-131 and Tc-99m, rain for natural Be-7, and soil erosion for fission generated Cs-137. Medical isotope data reflect the short term dynamics of medical usage, wastewater transport and treatment, and the river system. Be-7 data are influenced by the amount of rainfall on a short time scale, and by the size of the river catchment area and dilution due to tidal effects in the long term. Cs-137 values appear rather constant, behaving similarly to primordial K-40. In conclusion, the investigated radioisotopes offer a variety of possibilities to assess water and sediment dynamics. (author)

Rhenium radioisotopes for therapeutic radiopharmaceutical development

International Nuclear Information System (INIS)

Knapp, F.F. Jr.; Beets, A.L.; Pinkert, J.; Kropp, J.; Lin, W.Y.; Wang, S.Y.

2001-01-01

Rhenium-186 and rhenium-188 represent two important radioisotopes which are of interest for a variety of therapeutic applications in oncology, nuclear medicine and interventional cardiology. Rhenium-186 is directly produced in a nuclear reactor and the 90 hour half-life allows distribution to distant sites. The relatively low specific activity of rhenium-186 produced in most reactors, however, permits use of phosphonates, but limits use for labelled peptides and antibodies. Rhenium-188 has a much shorter 16.9 hour half-life which makes distribution from direct reactor production difficult. However, rhenium-188 can be obtained carrier-free from a tungsten-188/rhenium-188 generator, which has a long useful shelf-life of several months which is cost-effective, especially for developing regions. In this paper we discuss the issues associated with the production of rhenium-186- and rhenium-188 and the development and use of various radiopharmaceuticals and devices labelled with these radioisotopes for bone pain palliation, endoradiotherapy of tumours by selective catheterization and tumour therapy using radiolabelled peptides and antibodies, radionuclide synovectomy and the new field of vascular radiation therapy. (author)

Baseline quantity of 131I, 137Cs, 134Cs and 40K in urinary excretions from Thai people and internal exposure dose

Science.gov (United States)

Peekhunthod, D.; Bangvirunrak, J.; Sansakon, S.; Nukultham, A.; Pukkhaw, T.

2017-06-01

Today, sealed and unsealed radioactive materials have been used in Thailand for various purposes such as medical, agricultural and industrial applications. There is a growing trend in the use of radioactive materials. Moreover, neighboring countries are planning to construct and operate nuclear power plants. In case of nuclear power plant accidents, radioactive releases in environment and intakes into human body by inhalation and ingestion causing long term health effects. This research aims to determine the radiation baseline quantity of interested relevant radionuclides such as 131I, 137Cs, 134Cs as well as a natural radionuclide, 40K in urine samples of Thai people by gamma spectrometry. Two types of detectors (NaI and HpGe detectors) are calibrated by mixed radionuclide standards of 109Cd, 57Co, 133Ba, 54Mn, 137Cs and 60Co, (energy range from 88 to 1,331 keV). 720 urine samples are collected over a 24 hour period from Thai volunteers with the age older than 18 years old, who lived in eight locations of Thailand. To reduce the effect of geometric difference, 30 ml of urine samples are prepared for counting measurement and efficiency determination. The radiation baseline quantity of 131I, 137Cs, 134Cs and 40K in 30 ml of urine samples are 0.37±0.09, 0.63±0.13, 0.39±0.08 and 7.84±1.63 Bq, respectively. Based on the assumption of intake (50% of the intake by ingestion and 50% of the intake by inhalation), internal dose for members of public are assessed. The committed dose equivalent due to an intake of 131I, 137Cs, 134Cs and 40K are 2.36E-03±1.66-03, 1.15E-01±8.61E-02, 1.16E-01±7.77E-02, 9.44E-01±3.56E-01 mSv per year, respectively.

Dosimetric study of permanent prostate brachytherapy utilizing 131Cs, 125I and 103Pd seeds

International Nuclear Information System (INIS)

Yang Ruijie; Wang Junjie; Zhang Hongzhi

2009-01-01

Objective: To compare the dosimetric differences of permanent prostate brachytherapy utilizing 131 Cs, 125 I and 103 Pd seeds. Methods: Twenty-five patients with T 1 -T 2 c prostate cancer who had previously implanted with 125 I seeds were randomly selected in our study. The patients were re-planned with 131 Cs, 125 I and 103 Pd seeds by using the Prowess Brachytherapy 3.1 planning system to the prescription doses of 115 Gy, 145 Gy and 125 Gy, respectively. The seed strengths were 1.8 U,0.5 U and 1.8 U, respectively. The prostate, prostatic urethra and anterior wall of the rectum were contoured on trans-rectal ultrasound images. PTV was outlined based on the prostate volume with no margin applied. The attempted planning goals were that V 100 (the percentage volume of the prostate receiving at least 100% of the prescription doses)= 95%, D 90 (the minimum percentage dose covering 90% of the prostate volume) ≥100%, and prostatic urethra UD 10 (the maximum percentage dose receiving by 10% of the contoured urethra) ≤150%. For the plan comparison, we also computed prostate V 150 , prostatic urethra UV 120 , rectum RV 100 , and the number of implanted seeds and needles. The significance of the differences was tested using one way analysis of variance. Results: The average V 200 in the 103 Pd, 125 I and 131 Cs plans were 28.7%, 20.9% and 19.6% (F=42.50, P=0.000); the average V 150 were 51.9%, 42.1% and 39.4% (F=26.15, P=0.000); the average UV 120 were 26.9%, 29.5% and 23.8% (F=0.37, P=0.691); and the average rectum RV 100 were 0.31 cm 3 , 0.22 cm 3 and 0.19 cm 3 (F=0.43, P=0.652). For 103 Pd, 125 I and 131 Cs, the average number of implanted seeds per cm 3 prostate were 2.02, 2.01 and 1.87 (F=1.92, P=0.154), and the average number of needles were 33.6, 32.9 and 31.6 (F=0.26,P=0.772). Conclusions: Comparing to 125 I and 103 Pd seeds used in permanent prostate brachytherapy, 131 Cs seeds has better dose homogeneity, and possible better sparing of the urethra and rectum

COMS eye plaque brachytherapy dosimetry simulations for 103Pd, 125I, and 131Cs

International Nuclear Information System (INIS)

Melhus, Christopher S.; Rivard, Mark J.

2008-01-01

Monte Carlo (MC) simulations were performed to estimate brachytherapy dose distributions for Collaborative Ocular Melanoma Study (COMS) eye plaques. Brachytherapy seed models 200, 6711, and CS-1 Rev2 carrying 103 Pd, 125 I, and 131 Cs radionuclides, respectively, were modeled and benchmarked against previously published values. Calculated dose rate constants MC Λ were 0.684, 0.924, and 1.052 cGy h -1 U -1 (±2.6%, k=1 uncertainty) for models 200, 6711, and CS-1 Rev2, respectively. The seeds were distributed into 10, 12, 14, 16, 18, 20, and 22 mm-diameter COMS eye plaques. Simulations were performed in both heterogeneous and homogeneous environments, where the latter were in-water and the former included the silastic seed carrier insert and gold-alloy plaque. MC-based homogenous central axis dose distributions agreed within 2%±1% (±1 s.d.) to hand-calculated values. For heterogeneous simulations, notable photon attenuation was observed, with dose reduction at 5 mm of 19%, 11%, and 9% for 103 Pd, 125 I, and 131 Cs, respectively. A depth-dependent correction factor was derived to correct homogenous central-axis dose distributions for plaque component heterogeneities, which were found to be significant at short radial distances

Recent progress in radioisotope production in Vietnam

Energy Technology Data Exchange (ETDEWEB)

So, Le Van [Radioisotope Dept., Nuclear Research Institute, Dalat (Viet Nam)

1998-10-01

This is a report on the recent progress in radioisotope production in Vietnam. Using a nuclear research reactor of 500 KW with continuous operation cycles of 100 hours a month, the production of some important radioisotopes used in nuclear medicine and research was routinely carried out. More than 80 per cent of irradiation capacity of reactor for radioisotope production were exploited. The radioactivity of more than 150 Ci of {sup 131}I, {sup 99}Mo-{sup 99m}Tc, {sup 32}P, {sup 51}Cr, {sup 153}Sm, {sup 46}Sc, {sup 192}Ir was produced annually. Radiopharmaceuticals such as {sup 131}I-Hippuran and in-vivo Kits for {sup 99m}Tc labelling were also prepared routinely and regularly. More than 10 in-vivo Kits including modern radiopharmaceuticals such as HmPAO kit were supplied to hospitals in Vietnam. The research on the improvement of dry distillation technology for production of {sup 131}I was carried out. As a result obtained a new distillation apparatus made from glass was successfully put to routine use in place of expensive quartz distillation furnace. We have also continued the research programme on the development of {sup 99m}Tc generators using low power research reactors. Gel technology using Zr- and Ti- molybdate gel columns for {sup 99m}Tc generator production was developed and improved continually. Portable {sup 99m}Tc generator using Zr-({sup 99}Mo) molybdate gel column and ZISORB adsorbent column for {sup 99m}Tc concentration were developed. The ZISORB adsorbent of high adsorption capacity for {sup 99}Mo and other parent radionuclides was also studied for the development purpose of alternative technology of {sup 99m}Tc and other different radionuclide generator systems. The studies on the preparation of therapeutic radiopharmaceuticals labelling with {sup 153}Sm and {sup 131}I such as {sup 153}Sm-EDTMP, {sup 131}I-MIBG were carried out. (author)

Stability studies of therapeutic 131I-meta-iodobenzylguanidine (131I-mIBG) using high performance liquid chromatography

International Nuclear Information System (INIS)

Murhekar, V.V.; Mathur, Anupam; Pilkhwal, Neelam S.; Prabhakar, G.; Padmanabhan, D.; Sachdev, S.S.

2014-01-01

BRIT is a manufacturer and supplier of therapeutic doses (100 mCi) of the radiopharmaceutical 131 I-mIBG to various nuclear medicine centers in India. The therapeutic formulation is of high radioactive concentration (>10 mCi/ml) and is thus prone to radiolytic damage during transport, storage until administration. Earlier stability studies at this laboratory were done using conventional methods like Thin Layer Chromatography (TLC) which has an inherent limitation in terms of resolution. In view of this, a suitable HPLC method has been developed and the stability of therapeutic 131 I-mIBG was monitored at various conditions

Artificial radioisotopes in food chains

International Nuclear Information System (INIS)

Binnerts, W.T.; Faber, K.; Klijn, N.; Lemmens, C.; Wissink, M.

1986-01-01

Use of uranium for nuclear fission involves the risk of environmental contamination by radiation during the processes of mining, concentration, peaceful and military application and storage, reprocessing and waste disposal. Three of the most dangerous radioisotopes have been followed here as they move through four different food chains. The main bottlenecks for fast and massive transfer are for 131 I its rather short half life, for 137 Cs the defective plant uptake from soil (and much less so also the pathway through the animal body), and for 90 Sr its discrimination relative to calcium in several transport processes in the animal body, and its preference for the bone mass. Hence it is often of advantage for man to use animals as an additional food chain. Known exceptions are discussed: the reindeer and karibou living entirely on lichens during the winter and thereby acquiring for 137 Cs nearly identical specific activity as plant food, and cow's milk for iodine during a short period after contamination. 15 refs.; 1 figure; 4 tabs

A new radioisotope facility for Thailand

International Nuclear Information System (INIS)

Horlock, K.

1997-01-01

The Thai Office of Atomic Energy for Peace (OAEP) is planning a new Nuclear Research Centre which will be located at Ongkharak, a greenfield site some 100 km North of Bangkok. General Atomics (GA) has submitted a bid for a turnkey contract for the core facilities comprising a Reactor to be supplied by GA, an Isotope Production Facility supplied by ANSTO and a Waste Processing and Storage Facility to be supplied by Hitachi through Marubeni. The buildings for these facilities will be provided by Raytheon, the largest constructor of nuclear facilities in the USA. The proposed Isotope Facility will consist of a 3000 m 2 building adjacent to the reactor with a pneumatic radioisotope transfer system. Hot cells, process equipment and clean rooms will be provided, as well as the usual maintenance and support services required for processing radiopharmaceutical and industrial products. To ensure the highest standards of product purity the processing areas will be supplied with clean air and operated at slightly positive pressure. The radioisotopes to be manufactured include Phosphorus 32 (S-32 [n,p]P-32), I-131(Te-130 [n,g]Te-131[p]I-131) for bulk, diagnostic capsules and therapeutic capsules, Iridium 192 (Ir-191[n,g]Ir-192) wire for radiotherapy and discs for industrial radiography sources and bulk Iodine 125 (Xe-124[n,g]Xe-125[β]I-125 for radioimmunoassay. The bid includes proposals for training OAEP staff during design and development at ANSTO's radioisotope facilities, and during construction and commissioning in Thailand. The entire project is planned to take four years with commencement anticipated in early 1997. The paper will describe the development of the design of the hot-cells, process equipment, building layout and ventilation and other services

Current utilization of research reactor on radioisotopes production in China

International Nuclear Information System (INIS)

Liu Yishu

2000-01-01

The main technical parameters of the four research reactors and their current utilization status in radioisotope manufacture and labeling compounds preparation are described. The radioisotopes, such as Co-60 sealed source, Ir-192 sealed source, γ-knife source, I-131, I-125, Sm-153, P-32 series products, In-113m generator, Tc-99m gel generator, Re-188 gel generator, C-14, Ba-131, Sr-89, 90 Y, etc., and their labeling compounds prepared from the reactor produced radionuclides, such as I-131-MIBG, I-131-Hippure, I-131-capsul, Sm-153-EDTMP, Re-186-HEDP, Re-186-HA, C-14-urea, and radioimmunoassay kits etc. are presented as well. Future development plan of radioisotopes and labeling compounds in China is also given. Simultaneously, the possibility and methods of bilateral or multilateral co-operation in utilization of research reactor, personnel and technology exchange of radioisotope production and labeling compounds is also discussed. (author)

Current utilization of research reactor on radioisotopes production in China

Energy Technology Data Exchange (ETDEWEB)

Liu Yishu [Nuclear Power Institute of China, Chengdu (China)

2000-10-01

The main technical parameters of the four research reactors and their current utilization status in radioisotope manufacture and labeling compounds preparation are described. The radioisotopes, such as Co-60 sealed source, Ir-192 sealed source, {gamma}-knife source, I-131, I-125, Sm-153, P-32 series products, In-113m generator, Tc-99m gel generator, Re-188 gel generator, C-14, Ba-131, Sr-89, {sup 90}Y, etc., and their labeling compounds prepared from the reactor produced radionuclides, such as I-131-MIBG, I-131-Hippure, I-131-capsul, Sm-153-EDTMP, Re-186-HEDP, Re-186-HA, C-14-urea, and radioimmunoassay kits etc. are presented as well. Future development plan of radioisotopes and labeling compounds in China is also given. Simultaneously, the possibility and methods of bilateral or multilateral co-operation in utilization of research reactor, personnel and technology exchange of radioisotope production and labeling compounds is also discussed. (author)

Determination of the physiological root activity of fruit trees using the radioisotopes 131I

International Nuclear Information System (INIS)

Reckruehm, I.

1979-01-01

Using the radioisotope 131 I, the author made a study of the physiological root activity in a volume of soil and the activity of the individual root tips. The results show that the root activity is affected both by the size of the branch system of the crown and by the number of root tips in the given soil volume. The greater the number of branches supplied with iodine, the higher the activity of the root tips. The greater the number of root tips in a given soil volume, the lower the physiological activity of the individual root tips. (author)

Lung-conserving treatment of a pulmonary oligometastasis with a wedge resection and 131Cs brachytherapy.

Science.gov (United States)

Wernicke, A Gabriella; Parikh, Apurva; Yondorf, Menachem; Trichter, Samuel; Gupta, Divya; Port, Jeffrey; Parashar, Bhupesh

2013-01-01

Soft-tissue sarcomas most frequently metastasize to the lung. Surgical resection of pulmonary metastases is the primary treatment modality. Although lobectomy is widely acknowledged as the standard procedure to treat primary pulmonary tumors, the standard for pulmonary metastases is not well defined; furthermore, compromised lung function may tip the scales in favor of a less invasive approach. Here, we report the results of a patient treated with wedge resection and intraoperative cesium-131 ((131)Cs). A 58-year-old African American female was diagnosed with the American Joint Committee on Cancer Stage IIA mixed uterine leiomyosarcoma and underwent total abdominal hysterectomy and bilateral salpingo-oophorectomy followed by adjuvant external beam radiotherapy to a total dose of 45 Gy and vaginal brachytherapy to a total dose of 20 Gy. At 2 years, a routine CT scan of the chest revealed metastasis to right upper lobe of the lung. The patient's poor pulmonary function, related to a 45 pack-year smoking history and chronic emphysema, precluded a lobectomy. After the patient underwent a lung-sparing wedge resection of the pulmonary right upper lobe metastasis and intraoperative brachytherapy with (131)Cs seeds to a total dose of 80 Gy, she remained disease free in the implanted area. At a 2-year followup, imaging continued to reveal 100% local control of the area treated with wedge resection and intraoperative (131)Cs brachytherapy. The patient had no complications from this treatment. Such treatment approach may become an attractive option in patients with oligometastatic disease and compromised pulmonary function. Copyright © 2013 American Brachytherapy Society. Published by Elsevier Inc. All rights reserved.

Off-shore contamination by I-131 and Cs-137 from the Fukushima Daiichi nuclear power station accident

International Nuclear Information System (INIS)

Pereira, Wagner de Souza; Kelecom, Patrick Vicent; Miyashita, Erika; Universidade Federal Fluminense; Kelecom, Alphonse

2011-01-01

On March 11, 2011 the biggest earthquake ever registered in Japan severed off-site power supply to the Fukushima Daiichi Nuclear Power Station. Backup diesel generators began providing electricity to pumps circulating coolant to the reactors, but were knocked out by a large tsunami and the nuclear site lost the ability to maintain proper reactor cooling. This was the beginning of a huge nuclear accident that was assigned an INES maximum rating of 7. On March 21, Japanese authorities reported that the Tokyo Electric Power Company (TEPCO) had detected radioactive materials in seawater. Radioactivity started to be measured by the Japan Atomic Energy Agency every two days in sea water from eight locations, 30km from the coastline. I-131 and Cs-137 were analyzed among other radionuclides. It is the aim of this paper to gather all this information and to discuss the evolution of the radioactive marine contamination during the first month of the accident. Results indicate for surface seawater concentrations ranging from 24.9 to 161.0 Bq/L for I-131 and 11.2 to 186.0 Bq/L for Cs-137, and for deep waters of 1.59-15.0 Bq/L (I-131) and 0.0-11.4 Bq/L (Cs-137). The I-131 concentrations in superficial waters were at or above Japanese regulatory limits in the first days, then lowered during one week to increase again above limits when TEPCO released contaminated water into the ocean, to finally reach not detectable values the last week of April. With the exception of point 4, on April 15, the Cs-137 levels were always well below regulatory limits. (author)

Comparison of Dosimetric and Biologic Effective Dose Parameters for Prostate and Urethra Using 131Cs and 125I for Prostate Permanent Implant Brachytherapy

International Nuclear Information System (INIS)

Sahgal, Arjun; Jabbari, Siavash; Chen, Josephine; Pickett, Barbie; Roach, Mack; Weinberg, Vivian; Hsu, I-C.; Pouliot, Jean

2008-01-01

Purpose: To compare the urethral and prostate absolute and biologic effective doses (BEDs) for 131 Cs and 125 I prostate permanent implant brachytherapy (PPI). Methods and Materials: Eight previously implanted manually planned 125 I PPI patients were replanned manually with 131 Cs, and re-planned using Inverse Planning Simulated Annealing. 131 Cs activity and the prescribed dose (115 Gy) were determined from that recommended by IsoRay. The BED was calculated for the prostate and urethra using an α/β ratio of 2 and was also calculated for the prostate using an α/β ratio of 6 and a urethral α/β ratio of 2. The primary endpoints of this study were the prostate D 90 BED (pD 90 BED) and urethral D 30 BED normalized to the maximal potential prostate D 90 BED (nuD 30 BED). Results: The manual plan comparison (α/β = 2) yielded no significant difference in the prostate D 90 BED (median, 192 Gy 2 for both isotopes). No significant difference was observed for the nuD 30 BED (median, 199 Gy 2 and 202 Gy 2 for 125 I and 131 Cs, respectively). For the inverse planning simulated annealing plan comparisons (α/β 2), the prostate D 90 BED was significantly lower with 131 Cs than with 125 I (median, 177 Gy 2 vs. 187 Gy 2 , respectively; p = 0.01). However, the nuD 30 BED was significantly greater with 131 Cs than with 125 I (median, 192 Gy 2 vs. 189 Gy 2 , respectively; p = 0.01). Both the manual and the inverse planning simulated annealing plans resulted in a significantly lower prostate D 90 BED (p = 0.01) and significantly greater nuD 30 BED for 131 Cs (p = 0.01), compared with 125 I, when the prostate α/β ratio was 6 and the urethral α/β ratio was 2. Conclusion: This report highlights the controversy in comparing the dose to both the prostate and the organs at risk with different radionuclides

{sup 123}I and {sup 13I} purification for biomolecules labelling; Purificacao de {sup 123}I e {sup 131}I para marcacao de biomoleculas

Energy Technology Data Exchange (ETDEWEB)

Catanoso, Marcela Forli

2011-07-01

The {sup 123}I and {sup 131}I are iodine radioisotopes widely used in Nuclear Medicine. The radioisotope {sup 123}I is used in diagnosis through the SPECT technique and is routinely produced at IPEN in cyclotron through the reaction: '1{sup 24}Xe (p, 2n) '1{sup 23}Cs -> {sup 123}Xe -> {sup 123}I. The radioisotope {sup 131}I is used both in diagnosis and therapy due to its physical characteristics of decay by {beta}{sup -} and its {gamma}-ray emissions that are softened with the use of specific collimators for diagnosis. It is routinely produced at IPEN using the nuclear reactor through the indirect reaction: {sup 130}Te (n, {gamma}) ->{sup 131}Te -> {sup 131}I, irradiating compounds containing Te. The radiopharmaceuticals prepared with these radioisotopes go through rigorous quality control tests and the chemical purity of the primary radioisotopes {sup 123}I and {sup 131}I are within the permissible limits currently defined. However, the presence of some chemical contaminants can prejudice the biomolecules labeling (monoclonal antibodies and peptides), that will produce radiopharmaceuticals of first generation to the oncology area. The aim of this work was to obtain a new purification method of these radioisotopes, allowing the labeling of biomolecules and also to established a process control on those radioisotopes. The methodology was separated on 3 steps: Evaluation of '1{sup 23}I e {sup 131}I radionuclidic purity using a hyper pure germanium detector, chemical purity using ICP-OES and the retention and elution study of {sup 131}I in several absorbers to choose the most appropriate for the purification tests analyzing the behavior of the possible contaminants. The radionuclidic analyses showed the presence of Te and Co on {sup 131}I samples and Te, Tc e Co on {sup 123}I samples. The chemical purity analyses showed the presence of Al and Mo in {sup 123}I, coming from the window material of the target holder and the presence of Al and Te in {sup

Radiological accident with Iodine-131 in the Radioisotope Division at IPEN-CNEN/SP (Brazil)

International Nuclear Information System (INIS)

Sanches, Matias Puga; Rodrigues, Demerval Leonidas

1997-01-01

The accident occurred in the first week of May 1995, in the Radioisotope Division-TPI, involving two tubes containing a total volume of 3 ml, aqueous solution of N Al 1 31, with 370 MBq and 1480 MBq activity is reported. Part of installation and six workers involved in the distribution process were contaminated with 131 I, but there were no contamination outside the building. The workers were decontaminated and the received radiation doses were evaluated by the Radiotoxicological Laboratory of IPEN-CNEN/SP together with IRD-CNEN/RJ. The building involved was closed and the activities stopped until the complete decontamination by the Radioprotection experts of IPEN-CNEN/SP. (author)

Radiosensitizers action on Iodine 131 therapeutical effect

International Nuclear Information System (INIS)

Agote, Marcos; Kreimann, Erica L.; Bocanera, Laura V.; Dagrosa, Maria A.; Juvenal, Guillermo J.; Pisarev, Mario A.

1999-01-01

Present studies were aimed to research the possible application of a radiosensitizer, nicotinamide, to increase the therapeutical effect of radioiodine. There were used goitrous and normal rats with growing dose of Iodine 131, with and without simultaneous treatment with nicotinamide. The obtained results show that the nicotinamide treatment importantly increases the thyroid radio destructive effect induced by radioiodine. Under these experimental conditions, nicotinamide induces to a significant increase of thyroid vascularisation, without changes in the proteins ADP-ribosylation activity. These results show, for the first time, the radiosensitizer effect of nicotinamide in front of Iodine 131 and give the possibility of using it in the treatment of hyperthyroid or thyroid difference cancer patients. (author)

Multiple factor analysis of the therapeutic effect of 131I in treating 783 cases of Graves disease

International Nuclear Information System (INIS)

Cai Min; Li Xianfeng; Li Sijin; Chen Haibin

2008-01-01

Objective: To study the factors influencing therapeutic effect of 131 I in treating 783 cases of Graves disease. Methods: The values of various indexes were quantized on influencing factors such as age, sex, course of disease, mass of thyroid gland, the absorbed dose of 131 I per gram of thryoid gland, the given dose of 131 I, thyroid 24 h 131 I uptaking percentage, thyroid hormone and thyroid autoantibodys. The assessment of the therapeutic effect was made according to complete remission (including hypothyroidism) and partial remission after 131 I therapy. CMH χ 2 , Wilcoxon signed-rank test and Logistic regression were used to analyze the variable parameters before the treatment. Results: The therapeutic effect of 131 I is significant in the follow-up period (CMH χ 2 =69.21, P 131 I therapy for 12 months. The therapeutic effect was related to such factors as age thyroid mass, the absorbed dose of 131 I per gram of thryoid gland, thyroid 24 h 131 I uptaking percentage, etc (all the values of P 131 I uptaking percentage is higher, thyroid mass is bigger, thyroid gland is with noduses, the given dose of 131 I should be increased. Conversely decreased. (authors)

Radioisotopes and radiopharmaceuticals catalogue

International Nuclear Information System (INIS)

2002-01-01

The Chilean Nuclear Energy Commission (CCHEN) presents its radioisotopes and radiopharmaceuticals 2002 catalogue. In it we found physical characteristics of 9 different reactor produced radioisotopes ( Tc-99m, I-131, Sm-153, Ir-192, P-32, Na-24, K-42, Cu-64, Rb-86 ), 7 radiopharmaceuticals ( MDP, DTPA, DMSA, Disida, Phitate, S-Coloid, Red Blood Cells In-Vivo, Red Blood Cells In-Vitro) and 4 labelled compounds ( DMSA-Tc99m, DTPA-Tc99m, MIBG-I131, EDTMP-Sm153 ). In the near future the number of items will be increased with new reactor and cyclotron products. Our production system will be certified by ISO 9000 on March 2003. CCHEN is interested in being a national and an international supplier of these products (RS)

RNA Nanoparticles Derived from Three-Way Junction of Phi29 Motor pRNA Are Resistant to I-125 and Cs-131 Radiation

Science.gov (United States)

Li, Hui; Rychahou, Piotr G.; Cui, Zheng; Pi, Fengmei; Evers, B. Mark; Shu, Dan

2015-01-01

Radiation reagents that specifically target tumors are in high demand for the treatment of cancer. The emerging field of RNA nanotechnology might provide new opportunities for targeted radiation therapy. This study investigates whether chemically modified RNA nanoparticles derived from the packaging RNA (pRNA) three-way junction (3WJ) of phi29 DNA-packaging motor are resistant to potent I-125 and Cs-131 radiation, which is a prerequisite for utilizing these RNA nanoparticles as carriers for targeted radiation therapy. pRNA 3WJ nanoparticles were constructed and characterized, and the stability of these nanoparticles under I-125 and Cs-131 irradiation with clinically relevant doses was examined. RNA nanoparticles derived from the pRNA 3WJ targeted tumors specifically and they were stable under irradiation of I-125 and Cs-131 with clinically relevant doses ranging from 1 to 90 Gy over a significantly long time up to 20 days, while control plasmid DNA was damaged at 20 Gy or higher. PMID:26017686

SU-F-T-43: Prediction of Dose Increments by Brain Metastases Resection Cavity Shrinkage Model with I-125 and Cs-131 LDR Seed Implantations

Energy Technology Data Exchange (ETDEWEB)

Han, D; Braunstein, S; Sneed, P; McDermott, M; Ma, L [University of California San Francisco, San Francisco, CA (United States)

2016-06-15

Purpose: This work aims to determine dose variability via a brain metastases resection cavity shrinkage model (RC-SM) with I-125 or Cs-131 LDR seed implantations. Methods: The RC-SM was developed to represent sequential volume changes of 95 consecutive brain metastases patients. All patients underwent serial surveillance MR and change in cavity volume was recorded for each patient. For the initial resection cavity, a prolate-ellipsoid cavity model was suggested and applied volume shrinkage rates to correspond to 1.7, 3.6, 5.9, 11.7, and 20.5 months after craniotomy. Extra-ring structure (6mm) was added on a surface of the resection volume and the same shrinkage rates were applied. Total 31 LDR seeds were evenly distributed on the surface of the resection cavity. The Amersham 6711 I-125 seed model (Oncura, Arlington Heights, IL) and the Model Cs-1 Rev2 Cs-131 seed model (IsoRay, Richland, WA) were used for TG-43U1 dose calculation and in-house-programed 3D-volumetric dose calculation system was used for resection cavity rigid model (RC-RM) and the RC-SM dose calculation. Results: The initial resection cavity volume shrunk to 25±6%, 35±6.8%, 42±7.7%, 47±9.5%, and 60±11.6%, with respect to sequential MR images post craniotomy, and the shrinkage rate (SR) was calculated as SR=56.41Xexp(−0.2024Xt)+33.99 and R-square value was 0.98. The normal brain dose as assessed via the dose to the ring structure with the RC-SM showed 29.34% and 27.95% higher than the RC-RM, I-125 and Cs-131, respectively. The dose differences between I-125 and Cs-131 seeds within the same models, I-125 cases were 9.17% and 10.35% higher than Cs-131 cases, the RC-RM and the RC-SM, respectively. Conclusion: A realistic RC-SM should be considered during LDR brain seed implementation and post-implement planning to prevent potential overdose. The RC-SM calculation shows that Cs-131 is more advantageous in sparing normal brain as the resection cavity volume changes with the LDR seeds implementation.

Experimental determination of transfer coefficients of 137Cs and 131I from fodder into milk of cows and sheep after the Chernobyl accident

International Nuclear Information System (INIS)

Voigt, G.; Mueller, H.P.; Proehl, G.P.; Paretzke, H.G.; Propstmeier, G.; Roehrmoser, G.H.; Hofmann, P.

1989-01-01

Following the Chernobyl accident in April 1986, the transfer of 131 I and 137 Cs from feed to milk was studied under experimental and common agricultural conditions. From measurements in different dairy farms in Southern Bavaria, equilibrium transfer coefficients for cow's milk were calculated to be 0.003 d L-1 (range 0.0015 to 0.005) for 131 I and 0.003 d L-1 (range 0.0025 to 0.004) for 137 Cs. In feeding experiments with cows and sheep under more controlled conditions, milk transfer coefficients of 0.007 d L-1 (range 0.0055 to 0.0081) for 131 I and 0.003 d L-1 (range 0.0023 to 0.0053) for 137 Cs were obtained for cows, while for sheep the 137 Cs transfer coefficient was higher: 0.06 d L-1. The kinetics of the Cs transfer from fodder to cow's milk can be described by two exponential terms assuming biological half-lives in milk of 1-2 d and 10-20 d. The use of a fast component with 1.5 d and a fraction of 0.8, and a slow component with 15 d, gives a good approximation to the kinetics for all cows in this experiment

When are fume-cupboards necessary in hospital radioisotope laboratories

Energy Technology Data Exchange (ETDEWEB)

Birks, J L [Singleton Hospital, Swansea (UK)

1976-06-01

Suggestions are made for procedures likely to require the provision of efficient fume-cupboards in hospital radioisotope laboratories. All such departments undertaking in vivo radioisotope procedures will require a supply of sterile materials, but only some of these will also require a fume-cupboard, since the use of a relatively inexpensive aseptic cabinet, without air flow and exhaust system, may suffice for such procedures as the labelling of blood cells or plasma. Efficient fume-cupboards may be required in hospital laboratories that are routinely concerned with the elution of generators of isotopes such as /sup 99/Tcsup(m) and /sup 113/Insup(m), the sterilization of radiopharmaceuticals (e.g. technetium-sulphur colloid) requiring the use of a pressure cooker, and the storage and handling of therapeutic quantities of /sup 131/I. Copious general ventilation of isotope rooms may be preferable to the too frequent incorporation of unnecessary fume-cupboards.

Radiological accident with Iodine-131 in the Radioisotope Division at IPEN-CNEN/SP (Brazil); Acidente radiologico com iodo-131 nas instalacoes da Divisao de Radioisotopos do IPEN-CNEN/SP (Brasil)

Energy Technology Data Exchange (ETDEWEB)

Sanches, Matias Puga; Rodrigues, Demerval Leonidas [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

1997-12-31

The accident occurred in the first week of May 1995, in the Radioisotope Division-TPI, involving two tubes containing a total volume of 3 ml, aqueous solution of N Al{sup 1}31, with 370 MBq and 1480 MBq activity is reported. Part of installation and six workers involved in the distribution process were contaminated with {sup 131} I, but there were no contamination outside the building. The workers were decontaminated and the received radiation doses were evaluated by the Radiotoxicological Laboratory of IPEN-CNEN/SP together with IRD-CNEN/RJ. The building involved was closed and the activities stopped until the complete decontamination by the Radioprotection experts of IPEN-CNEN/SP. (author) 2 refs., 1 fig., 1 tab.; e-mail: msanches at net.ipen.br; dirodri at net.ipen.br

Chondroitin Sulfate (CS) Lyases: Structure, Function and Application in Therapeutics.

Science.gov (United States)

Rani, Aruna; Patel, Seema; Goyal, Arun

2018-01-01

Glycosaminoglycans (GAGs) such as chondroitin sulfate (CS) are the chief natural polysaccharides which reside in biological tissues mainly in extracellular matrix. These CS along with adhesion molecules and growth factors are involved in central nervous system (CNS) development, cell progression and pathogenesis. The chondroitin lyases are the enzyme that degrade and alter the CS chains and hence modify various signalling pathways involving CS chains. These CS lyases are substrate specific, can precisely manipulate the CS polysaccharides and have various biotechnological, medical and therapeutic applications. These enzymes can be used to produce the unsaturated oligosaccharides, which have immune-modulatory, anti-inflammatory and neuroprotective properties. This review focuses on the major breakthrough of the chondroitin sulfate degrading enzymes, their structures and functioning mechanism. This also provides comprehensive information regarding production, purification, characterization of CS lyases and their major applications, both established as well as emerging ones such as neural development. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

Clinical Investigation and Treatment of Thyroid Disease with Radioactive Iodine (131I)

International Nuclear Information System (INIS)

Lee, Mun Ho; Koh, Chang Soon; Ro, Heung Kyu; Koo, In Seu; Suh, Whan Jo; Lee, Kyung Ja; Lee, Hong Kyu; Lee, Chung Sang

1970-01-01

A summary of the clinical data of the 131 I-thyroid function tests and the therapeutic results of 131 I among the 2,658 patients of various thyroid diseases treated over the past 10 years from May 1960 to Oct. 1969 at the Radioisotope Clinic and Laboratory, SNUH were presented and discussed. 1) The patients examined consisted of 929 cases (34.9%) of diffuse toxic goiter, 762 cases (28.7%) of diffuse nontoxic goiter, 699 cases (26.3%) of nodular nontoxic goiter, 58 cases (2.2%) of nodular toxic goiter and 210 cases (7.9%) of hypothyroidism. 2) There were 300 (11.4%) male and 2358 (88.6%) female, showing a ratio of 1 : 8. 3) The majority of patients (79.1%) were in the 3rd-5th decade of their lives. 3) The normal ranges, diagnostic values of 131 I uptake test, 48 hrs serum activity, BMR and main subjective symptoms of various thyroid diseases were discussed. 5) In the 579 patients among 867 cases with hyperthyroidism treated with 131 I, 47.8% were confirmed to be cured completely after single therapeutic doses. 6) The complications of 131 I therapy were discussed and myxedema had developed in 6.75% of our patients. 7) The results of 131 I thyroid function tests were analysed among the 160 cases of thyroid diseases which were confirmed the diagnosis with histopathological measures.

Isolation time determination of patients with differentiated thyroid carcinoma treated with therapeutic doses of 131 radioiodine

International Nuclear Information System (INIS)

Sierralta, M.P.; Lillo, R.; Massardo, T.; Jofre, M.J.

2002-01-01

Isolation time determination of patients with differentiated thyroid carcinoma treated with therapeutic doses of 131 radioiodine. Introduction: The coadyuvant treatment with 131 I had proven to be useful in patients with differentiated thyroid carcinoma (DTC). Due to the physical characteristics of this radioisotope these patients must be absolutely isolated in order to reduce the radioactive exposure to other individuals. The aim of the study was to determine the time required to reach the maximum permissible radiation exposure level (0,25mR/h) to general public. Material between August 1999 and May 2000, 30 patients with DTC diagnosis in the University of Chile Clinical Hospital Nuclear Medicine Centre were studied, 25 women (83%) and 5 men (17%), mean age 45 years old (15-71 range). Tumoral histology was 86% papillary and 14% follicular types. Thirty one doses of 131 I were administered ( one patient received 2 doses): 24 of 100 mCi (77%), 5 of 150 mCi (16%) and 2 of 200 mCi (7%); afterwards the 1 m exposition rate in air was measured at neck level with a Geiger-Mueller detector. The procedure was repeated on day 4 and every day following until the predicted radiation exposure levels were reached. Results: The average exposure rate at day 0 ( after given the radiopharmaceutical) was 20,12 mR/h (4-32 range). At day 4 the average rate was 0,21 mR/h (0,08-0,34 ), and 61% (n=19) of the patients reached 0,25 mR/h within that day. On day 5 10% (n=3) reached 0,25 mR/h (0,25-0,26), on day 6 16% (n=5) reached 0,25 mR/h (0,2-0,28), on day 7 6% (n=2) reached 0,39 mR/h (0,25-0,48) and the remaining 7% on day 13 and day 17 (n=2). Conclusion After a treatment dose of 131 iodine over 60% of the cases can finish the isolation on day 4, and 90% on day 7. The measurement of 131 I uptake after 24 hours will help to determine the evolution of post treatment levels

Isolation time determination of patients with differentiated thyroid carcinoma treated with therapeutic doses of 131 radioiodine

Energy Technology Data Exchange (ETDEWEB)

Sierralta, M P [University of Chile Clinical Hospital Nuclear Medicine Centre, Santiago (Chile); Military Hospital Nuclear Medicine Department , Santiago (Chile); Lillo, R; Massardo, T [University of Chile Clinical Hospital Nuclear Medicine Centre, Santiago (Chile); Jofre, M J [Military Hospital Nuclear Medicine Department, Santiago (Chile)

2002-09-01

Isolation time determination of patients with differentiated thyroid carcinoma treated with therapeutic doses of 131 radioiodine. Introduction: The coadyuvant treatment with 131 I had proven to be useful in patients with differentiated thyroid carcinoma (DTC). Due to the physical characteristics of this radioisotope these patients must be absolutely isolated in order to reduce the radioactive exposure to other individuals. The aim of the study was to determine the time required to reach the maximum permissible radiation exposure level (0,25mR/h) to general public. Material between August 1999 and May 2000, 30 patients with DTC diagnosis in the University of Chile Clinical Hospital Nuclear Medicine Centre were studied, 25 women (83%) and 5 men (17%), mean age 45 years old (15-71 range). Tumoral histology was 86% papillary and 14% follicular types. Thirty one doses of 131 I were administered ( one patient received 2 doses): 24 of 100 mCi (77%), 5 of 150 mCi (16%) and 2 of 200 mCi (7%); afterwards the 1 m exposition rate in air was measured at neck level with a Geiger-Mueller detector. The procedure was repeated on day 4 and every day following until the predicted radiation exposure levels were reached. Results: The average exposure rate at day 0 ( after given the radiopharmaceutical) was 20,12 mR/h (4-32 range). At day 4 the average rate was 0,21 mR/h (0,08-0,34 ), and 61% (n=19) of the patients reached 0,25 mR/h within that day. On day 5 10% (n=3) reached 0,25 mR/h (0,25-0,26), on day 6 16% (n=5) reached 0,25 mR/h (0,2-0,28), on day 7 6% (n=2) reached 0,39 mR/h (0,25-0,48) and the remaining 7% on day 13 and day 17 (n=2). Conclusion After a treatment dose of 131 iodine over 60% of the cases can finish the isolation on day 4, and 90% on day 7. The measurement of 131 I uptake after 24 hours will help to determine the evolution of post treatment levels.

Vertical migration of 85Sr, 137Cs and 131I in various arable and undisturbed soils

International Nuclear Information System (INIS)

Palagyi, S.; Palagyiova, J.

2003-01-01

The vertical migration of 85 Sr, 137 Cs and 131 I in some arable and undisturbed single-contaminated soils was studied by gamma-spectrometry measurements under lysimetric laboratory conditions during irrigation of the soil profiles with wet atmospheric precipitation for about one year, except 131 I. A new simple exponential compartment (box) model was derived, which makes it possible to calculate the migration rate constants and migration rates in the individual soil layers (vertical sections) as well as the total vertical migration rate constants and total vertical migration rates of radionuclides in the bulk soil horizon. The relaxation times of radionuclides in respective soil horizons can also be evaluated. (author)

Interconnection Studies of Subsurface River Between Bribin and Ngreneng by Using Radioisotope Tracer Iodium-131

International Nuclear Information System (INIS)

Wibagiyo

2004-01-01

Interconnection Studies of Subsurface River Between Bribin and Ngreneng by Using Radioisotope Tracer Iodium-131, carried out in 2002, the similar studies was also conducted in 2000 from subsurface river in Jurang Jero sinkhole, where the radioactivity appeared at Bribin cave 4 hours and 8 hours at Ngreneng cave. There is a question whether a subsurface river is flowing from Jurang Jero sinkhole to Bribin cave and then to Ngreneng cave, or from Jurang Jero sinkhole there is junction to Bribin and to Ngreneng. in 2002 a Germany team founded junction on up stream of river in Bribin cave, from the junction was carried out tracing which monitoring in Ngreneng cave. Where the result a junction connecting with Ngreneng cave, but the main stream in Bribin not connecting with Ngreneng. (author)

Development of radioisotope production in the Philippines

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, E G [Philippine Nuclear Research Institute, Quezon (Philippines)

1998-10-01

The Philippine Nuclear Research Institute (PNRI) started its activities on radioisotope production more than three decades ago, when the Philippine Research Reactor (PRR-1) started operating at its full rated power of 1 MW. Since then, several radionuclides in different chemical forms, were routinely produced and supplied for use in nuclear medicine, industry, agriculture, research and training, until the conversion of the PRR-1 to a 3 MW TRIGA type reactor. After the criticality test of the upgraded reactor, a leak was discovered in the pool liner. With the repair of the reactor still ongoing, routine radioisotope production activities have been reduced to dispensing of imported bulk {sup 131}I. In the Philippines, radioisotopes are widely used in nuclear medicine, with {sup 131}I and {sup 99m}Tc as the major radionuclides of interest. Thus the present radioisotope production program of PNRI is directed to meet this demand. With the technical assistance of the International Atomic Energy Agency (IAEA), PNRI is setting up a new {sup 131}I production facility. The in-cell equipment have been installed and tested using both inactive and active target, obtained from BATAN, Indonesia. In order to meet the need of producing {sup 99}Mo-{sup 99m}Tc generators, based on low specific activity reactor-produced {sup 99}Mo, research and development work on the preparation of {sup 99m}Tc gel generators is ongoing. (author)

Therapeutic Effect of 131I for 230 Patients with Hyperthyroidism

International Nuclear Information System (INIS)

He Yujie; Zhang Chengxi; Hu Jiqing; Guo Sihui; Yuan Hui; Li Jing

2009-01-01

To evaluate the therapeutic effect of 131 I in treatment of patients with hyperthyroidism and analysis the factors that influence the effect, 230 cases of hyperthyroidism were treated with 131 I, and were followed-up at 1.5, 3, 6, 12 months and even longer time after 131 I radiotherapy. The serum levels of FT3, FT4 and TSH were detected in all cases. The results showed that 181 patients were cured (78.6%), 22 patients were improved (9.5%), 23 cases developed early hypothyroidism(10.0%),and 4 cases developed later hypothyroidism. 12 cases in 27 patients with hypothyroidism treated with thyroxin were recovered, but the other 15 cases need to be given permanent treatment. The factors which influence 131 I radiotherapeutic effect include the patient age, course of disease,application of ATD, size and quality of thyroid, and the level of thyroid hormone. The patients should be followed up to prevent occurrence of hypothyroidism. The early hypothyroidism should be treated in order to decrease the permanent hypothyroidism rate. (authors)

Methodology for management of therapeutic dose of I-131

International Nuclear Information System (INIS)

Basteris M, J.; Gomez D, R.

2007-01-01

The present work suggests the use of measures guided to eliminate the resulting chronic sialoadenitis of the treatment previously described with a therapeutic dose bigger than ablative of Iodine 131, as well as the use of citric fruits to stimulate the salivation, the administration of liquid post-dose is included to accelerate the gastric emptying avoiding the secondary effects as the vomit. (Author)

Fallout and drinking water contamination by I-131 and Cs-134, 137 in Japan, from the Fukushima Daiichi NPS accident

Energy Technology Data Exchange (ETDEWEB)

Kelecom, Alphonse; Miyashita, Erika; Kelecom, Patrick Vicent [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

2011-07-01

The earthquake followed by a tsunami in Japan, on last March 11, seriously damaged four of the six reactors of the Fukushima Daiichi nuclear power station (NPS). Radioactive smokes and highly contaminated water were released for weeks to the environment. Since March 12, when the plant operator TEPCO and Japan's nuclear agency (NISA) confirmed the presence of radionuclides near the NPS, a giant environmental monitoring operation was set up, covering the entire Japanese territory. Daily thousands measurements are realized. We here analyze data released during 60 days on I-131 and Cs-134,137 radioactive concentrations in drinking water and fallout for 45 prefectures. Miyagi and Fukushima, that requires a separate study, are not considered here. Drinking water contamination by I-131 was observed in 13 prefectures, including Tokyo. The most impacted one was Tochigi (maximum of 110 Bq/l, March 24). This value turned water not drinkable for infants and babies. Cs-137 was detected in drinking water in 8 prefectures, with a maximum level of 18 Bq/l in Ibaraki. These levels do not affect potability of tap water. I-131 was observed in fallout in 27 prefectures, with level reaching 93 kBq/m2 in Ibaraki and 36 kBq/m{sup 2} in Tokyo on March 21 and 23 respectively. Fallout of Cs-137 was observed in 19 prefectures. The maximum deposition occurred again in Ibaraki (13kBq/m{sup 2}, March 21) and in Tokyo (5.3 kBq/m2, March 22). Since mid April, only trace contamination has been observed for both radionuclides in drinking water. Sporadically medium levels of Cs-137 are still observed in fallout. (author)

Fallout and drinking water contamination by I-131 and Cs-134, 137 in Japan, from the Fukushima Daiichi NPS accident

International Nuclear Information System (INIS)

Kelecom, Alphonse; Miyashita, Erika; Kelecom, Patrick Vicent

2011-01-01

The earthquake followed by a tsunami in Japan, on last March 11, seriously damaged four of the six reactors of the Fukushima Daiichi nuclear power station (NPS). Radioactive smokes and highly contaminated water were released for weeks to the environment. Since March 12, when the plant operator TEPCO and Japan's nuclear agency (NISA) confirmed the presence of radionuclides near the NPS, a giant environmental monitoring operation was set up, covering the entire Japanese territory. Daily thousands measurements are realized. We here analyze data released during 60 days on I-131 and Cs-134,137 radioactive concentrations in drinking water and fallout for 45 prefectures. Miyagi and Fukushima, that requires a separate study, are not considered here. Drinking water contamination by I-131 was observed in 13 prefectures, including Tokyo. The most impacted one was Tochigi (maximum of 110 Bq/l, March 24). This value turned water not drinkable for infants and babies. Cs-137 was detected in drinking water in 8 prefectures, with a maximum level of 18 Bq/l in Ibaraki. These levels do not affect potability of tap water. I-131 was observed in fallout in 27 prefectures, with level reaching 93 kBq/m2 in Ibaraki and 36 kBq/m 2 in Tokyo on March 21 and 23 respectively. Fallout of Cs-137 was observed in 19 prefectures. The maximum deposition occurred again in Ibaraki (13kBq/m 2 , March 21) and in Tokyo (5.3 kBq/m2, March 22). Since mid April, only trace contamination has been observed for both radionuclides in drinking water. Sporadically medium levels of Cs-137 are still observed in fallout. (author)

Comparison of radiolabeling efficiency of peptides containing the RGD domain using the Tc-99M and I-131 radioisotopes

International Nuclear Information System (INIS)

Sobral, Danielle V.; Cabral, Francisco Romero; Malavolta, Luciana

2017-01-01

Full text: Introduction: Radiolabeled peptides have become very important in nuclear medicine and oncology in recent years mainly because they represent the molecular basis for in vivo imaging and radiopharmaceutical therapy with high specificity and affinity for over expressed receptors in tumors (Thno 2(5):481-501, 2012 / Drug Discov. Today. 7:1224-1232, 2012). In this context, peptides containing the RGD domain which possess high affinity for the αvβ3 integrin receptor have become an important tool in a wide variety tumor, including glioblastoma (Exp. Opin. Drug Deliv. 8:1041- 1056, 2011). Objective: The goal of this work was to compare the radiolabeling efficiency of the GRGDYV and GRGDHV peptides when radiolabeled with the 131 I and 99m Tc radioisotopes, respectively, as well as, to evaluate the features of synthesized complexes. Methods: The GRGDYV and GRGDHV fragments were manually synthesized by peptide synthesis in solid phase accordingly to the Fmoc protocol and purified by preparative HPLC. The GRGDYV and GRGDHV peptides were radiolabeled with the I-131 and Tc-99m radioisotopes respectively, through of the direct method of radiolabeling. The radioiodination was evaluated and optimized using the methodology of Chloramine-T and for the peptide containing the histidine aminoacid the tricarbonyl method was used. Radiochemical yield analyses of [ 131 I]-GRGDYV and [ 99m Tc]-GRGDHV peptides were performed by thin layer chromatography on silica gel TLC-SG (Al) in ACN 95%. The radiolabeled peptides were purified by using solid phase extraction (Sep-Pak C18 filter). The stability studies were realized at 2, 24, 48 and 72 hours in room temperature and refrigerate (4 deg C) for [ 131 I]-GRGDYV and up to 6 hours for the fragment [ 99m Tc]-GRGDHV. Partition coefficient was determinate for both radiopeptides. Results: The peptides [ 131 I]-GRGDYV and [ 99m Tc]-GRGDHV were efficiently synthesized, radiolabeled and showed radiochemical yield of 91.02% ± 1.68 (n=5

Experience in treatment of hyperthyroidism with I-131 diagnosis, patient preparation and therapeutic procedure

International Nuclear Information System (INIS)

Zhongyun, Pan

2003-01-01

Treatment of hyperthyroidism with I-131 diagnosis is being performed after clinical diagnosis of thyrotoxicosis based on clinical manifestations of hypermetabolic state, serumT3 and T4 determination; medical preparation of patients and therapeutic procedure is obtained for better efficacy, relieve symptoms and prevent aggravation of thyrotoxicosis after I-131 treatment

Radiological protection guidance for radioactive patients -new data for therapeutic 131I

International Nuclear Information System (INIS)

Hilditch, T.E.; Watson, W.S.; Connell, J.M.C.; Davies, D.L.; Alexander, W.D.

1991-01-01

Thyroidal retention of 131 I was measured in 77 thyrotoxic patients over a period of 1-50 days after a first therapeutic administration of the radionuclide. Mean 131 I activity in the gland (± S.D.) at 1 day was 56.1 ± 11.1% of the administered dose activity and thereafter retention followed a single exponential decay pattern with a mean effective half-life (± S.E.M.) of 6.35 ± 0.14 days. In patients who required further 131 I therapy, there was evidence that retention could be markedly reduced if there was virtual ablation of thyroid tissue. It is proposed that these retention data can be used to determine body radioactivity at any interval after the administration of 131 I for treatment of thyrotoxicosis, thus obviating the need for serial measurements in every individual patient. (author)

The therapeutic use of I-131 meta-iodobenzylguanidine (MIBG) in neuroblastoma

International Nuclear Information System (INIS)

Hartmann, O.; Lumbroso, J.D.; Lemerle, J.; Schlumberger, M.; Parmentier, C.; Ricard, M.; Aubert, B.; Coornaert, S.; Merlin, L.

1988-01-01

Despite the use of intensified conventional chemotherapy the complete response rate of advanced neuroblastoma remains low. The use of high-dose chemo-radiotherapy followed by bone marrow transplantation (BMT) improved the duration of disease free survival but, even after these high-dose regimens the relapse rate remains high. Metaiodobenzylguanidine (MIBG) labelled with I-131 or I-123 can be used for scintigraphic imaging of neuroblastoma. In order to evaluate the therapeutic role of I-131-MIBG in the treatment of neuroblastoma patients, a phase II study was performed in 12 patients. Results are presented in this paper

Calculating of Dose Distribution in Tongue Brachytherapy by Different Radioisotopes using Monte Carlo Simulation and Comparing by Experimental Data

Directory of Open Access Journals (Sweden)

Banafsheh Zeinali Rafsanjani

2011-06-01

Full Text Available Introduction: Among different kinds of oral cavity cancers, the frequency of tongue cancer occurrence is more significant. Brachytherapy is the most common method to cure tongue cancers. Long sources are used in different techniques of tongue brachytherapy. The objective of this study is to asses the dose distribution around long sources, comparing different radioisotopes as brachytherapy sources, measuring the homogeneity of delivered dose to treatment volume and also comparing mandible dose and dose of tongue in the regions near the mandible with and without using shield. Material and Method: The Monte Carlo code MCNP4C was used for simulation. The accuracy of simulation was verified by comparing the results with experimental data. The sources like Ir-192, Cs-137, Ra-226, Au-198, In-111 and Ba-131 were simulated and the position of sources was determined by Paris system. Results: The percentage of mandible dose reduction with use of 2 mm Pb shield for the sources mentioned above were: 35.4%, 20.1%, 86.6%, 32.24%, 75.6%, and 36.8%. The tongue dose near the mandible with use of shied did not change significantly. The dose homogeneity from the most to least was obtained from these sources: Cs-137, Au-198, Ir-192, Ba-131, In-111 and Ra-226. Discussion and Conclusion: Ir-192 and Cs-137 were the best sources for tongue brachytherapy treatment but In-111 and Ra-226 were not suitable choices for tongue brachytherapy. The sources like Au-198 and Ba-131 had rather the same performance as Ir-192

Comparison of radiolabeling efficiency of peptides containing the RGD domain using the Tc-99M and I-131 radioisotopes

Energy Technology Data Exchange (ETDEWEB)

Sobral, Danielle V.; Cabral, Francisco Romero; Malavolta, Luciana [Santa Casa de São Paulo, SP (Brazil). Faculdade de Ciências Médicas; Durante, Ana C. Ranucci; Miranda, Ana C. Camargo; Barbosa, Marycel R. F.Figols de [Instituto Israelita de Ensino e Pesquisa Albert Einstein, São Paulo, SP (Brazil)

2017-07-01

Full text: Introduction: Radiolabeled peptides have become very important in nuclear medicine and oncology in recent years mainly because they represent the molecular basis for in vivo imaging and radiopharmaceutical therapy with high specificity and affinity for over expressed receptors in tumors (Thno 2(5):481-501, 2012 / Drug Discov. Today. 7:1224-1232, 2012). In this context, peptides containing the RGD domain which possess high affinity for the αvβ3 integrin receptor have become an important tool in a wide variety tumor, including glioblastoma (Exp. Opin. Drug Deliv. 8:1041- 1056, 2011). Objective: The goal of this work was to compare the radiolabeling efficiency of the GRGDYV and GRGDHV peptides when radiolabeled with the {sup 131}I and {sup 99m}Tc radioisotopes, respectively, as well as, to evaluate the features of synthesized complexes. Methods: The GRGDYV and GRGDHV fragments were manually synthesized by peptide synthesis in solid phase accordingly to the Fmoc protocol and purified by preparative HPLC. The GRGDYV and GRGDHV peptides were radiolabeled with the I-131 and Tc-99m radioisotopes respectively, through of the direct method of radiolabeling. The radioiodination was evaluated and optimized using the methodology of Chloramine-T and for the peptide containing the histidine aminoacid the tricarbonyl method was used. Radiochemical yield analyses of [{sup 131}I]-GRGDYV and [{sup 99m}Tc]-GRGDHV peptides were performed by thin layer chromatography on silica gel TLC-SG (Al) in ACN 95%. The radiolabeled peptides were purified by using solid phase extraction (Sep-Pak C18 filter). The stability studies were realized at 2, 24, 48 and 72 hours in room temperature and refrigerate (4 deg C) for [{sup 131}I]-GRGDYV and up to 6 hours for the fragment [{sup 99m}Tc]-GRGDHV. Partition coefficient was determinate for both radiopeptides. Results: The peptides [{sup 131}I]-GRGDYV and [{sup 99m}Tc]-GRGDHV were efficiently synthesized, radiolabeled and showed

Production of radioisotopes with BR2 facilities

International Nuclear Information System (INIS)

Fallais, C.J.; Morel de Westfaver, A.; Heeren, L.; Baugnet, J.M.; Gandolfo, J.M.; Boeykens, W.

1978-01-01

After a brief account on the isotopes production evolution in the industrialized countries the irradiation devices and the types of standardized capsules used in the BR2 reactor are described as well as the thermal neutron flux. Production of most important radioisotopes like 131 Iodine, 60 Cobalt, 192 Iridium and 99 Molybdenum and their main utilizations (uses)are described. The mean specific activities and the limit of use for different radioisotopes are reported. (A.F.)

Methodology for management of therapeutic dose of I-131; Metodologia para administrar dosis terapeutica de I-131

Energy Technology Data Exchange (ETDEWEB)

Basteris M, J.; Gomez D, R. [Universidad Autonoma de Yucatan, Facultad de Medicina, Merida, Yucatan (Mexico)

2007-07-01

The present work suggests the use of measures guided to eliminate the resulting chronic sialoadenitis of the treatment previously described with a therapeutic dose bigger than ablative of Iodine 131, as well as the use of citric fruits to stimulate the salivation, the administration of liquid post-dose is included to accelerate the gastric emptying avoiding the secondary effects as the vomit. (Author)

Present status of unsealed radioisotope therapy in Japan based on the nation-wide questionnaire

International Nuclear Information System (INIS)

Oyamada, Hiyoshimaru

1999-01-01

In Japan, clinical application of unsealed radioisotopes is strictly regulated. Especially in the field of therapy, we are allowed to use only Na 131 I at present. Under such circumstances, the present status of therapeutic nuclear medicine in Japan was surveyed by means of a nation-wide questionnaire, conducted in 193 hospitals. Then, 113 hospitals replied to such questionnaire (recovery rate: 58.5%), and it was found that in 77 hospitals, radioisotope therapy is being performed for Graves' disease and/or thyroid cancer. The questionnaire covered the following points: for Graves' disease-the basic strategy of 131 I therapy, its indications, absorbed doses planned to be given, whether the therapy had been conducted on outpatient basis or in-patient basis, method of thyroid weight estimation, interval of administration in case of multiple doses, number of patients treated per year (1996) etc., and for thyroid cancer-strategy for thyroid remnant, the doses to be given, the maximum doses permitted by the authorities in each hospital both per day and per year, handling of highly contaminated urine in each hospital, interval of administration in case of multiple doses, number of patients treated per year (1996) etc. Also questioned were dissatisfaction with the present regulation by the authorities and/or requests for the better daily work, if any. Based on the above questionnaire, the present status of unsealed radioisotope therapy in Japan was investigated. (author)

Synthesis and granulation of a titanosilicate with adsorption capacity for Cs to be used for treating de ILLW of the Ezeiza Radioisotope Production Plant

International Nuclear Information System (INIS)

Curi, Rodrigo; Bianchi, Hugo L; Luca, Vittorio

2012-01-01

The sitinakite structured titanosilicate is widely used for treating ILLW thanks to its capacity for adsorbing both Cs-137 and Sr-90. Its effectiveness lies in its incredibly high selectivity for such radioisotopes, which makes it useful in complex isotope solutions and even in strong acid and alkaline conditions. In Argentina, an off-the-shelve titanosilicate was used in Ezeiza's radioisotope production plant. Because of commercial restrictions, it is no longer available so an inhouse production is being developed. The aim of this project consists of the following: 1. Synthesis of titanosilicate and structural characterization 2. Adsorption kinetics of Cs + 3. Upscale of the synthesis process 4. Assessment of the influence of synthesis temperature and time on product crystallinity 5. Measurement of adsorption capacity of commercial titanosilicates IE910, IE911 and novel RC15H 6. Separative performance column essay and breakthrough plot 7. Chemical and radiolysis resistance of the adsorbent powder binder Polyacrylonitrile (PAN) in contact with the actual waste Throughout this work we have studied the optimum synthesis conditions capable of rendering a sitinakite structured titanosilicate, assessed its Cs + adsorption kinetics, adsorption capacity, crystal phase and purity via DRX, particle size with Laser Light Scattering technique. We have also conducted column breakthrough experiments and tried the chemical and radiolysis resistance of the final product (author)

Transport of 131I and 137Cs from air to cows milk produced in north-western Italian farms following the Chernobyl accident

International Nuclear Information System (INIS)

Spezzano, P.; Giacomelli, R.

1991-01-01

After the Chernobyl accident, the levels of 131 I and 137 Cs were measured in surface air, pasture grass and milk produced by cows fed exclusively on fresh grass. The observed values of the vegetation-to-air, milk-to-vegetation and milk-to-air concentration ratios were compared with the values predicted by an internationally recognized assessment model for the transfer of radionuclides through terrestrial food chains. Predicted values were higher than the observed results by factors of 2.6, 2.1 and 5.6 for 131 I and 4.3, 3.7 and 16 for 137 Cs, for the vegetation-to-air, milk-to-vegetation and milk-to-air ratios, respectively. A better agreement between prediction and observation was achieved by using experimental values of the following parameters; the mass interception factor (R/Y), the effective decay constants on vegetation (λ ν ) and the milk transfer coefficients (F m ), these being lower than the model default values. Milk produced by dairy cows fed on a mixed diet showed a different behaviour with regard to excretion of 137 Cs. (author)

Management system in the dose assessment due to the intake of "1"3"1I in occupationally exposed workers (OEW) in a radioisotope production plant

International Nuclear Information System (INIS)

Koga, Roberto; Jara, Raul; Defilippi, Luis; Osores, Jose

2015-01-01

This article presents the evaluation and management processes due to the incorporation of "1"3"1I in occupationally exposed workers (OEW) of a Radioisotope Production Plant by in vivo measurement of the retained activity of this radionuclide in thyroid. The procedures for the occupational control of the OWE were established, including intermediate checks and calibration of the equipment according to the NTP ISO/IEC 17025:2006 standard. (author)

Radiation doses by therapeutical practices with iodine 131

International Nuclear Information System (INIS)

Di Trano, J.L.; Rojo, A.M.; Gomez Parada, I.M.; Grassi, E.; Gatica, N.; Kunst, J.J.; Gonzalez, M.

1998-01-01

The aim of this document is to estimate the doses to workers and public due to therapeutical practices with iodine 131. Environmental and personal doses by external irradiation were determined using thermoluminescent dosimeters (TLD). The environmental dosimetry resulted in an equivalent dose H * (10) of approximately 0,1 mSv. The calculated personal equivalent dose Hp (10) was of the order of 0,1 mSv. The exposition rate was measured, being the values obtained in the range of 0,20 and 0,35 mSv/h. (1m from the abdominal wall). Concentrations of iodine 131 were determinate in the air of the room, during the first day in the hospital. Values obtained were between 0,04 Bq/l and 0,20 Bq/l. Surface samples were taken in the service, obtaining levels of contamination in the range of 0,001 and 0,4 Bq/cm 2 . The surface samples obtained in the hospital room were about 0,15 Bq/cm 2 . Urine samples were collected resulting in an eliminated activity of iodine 131, during the first 24 hours, of about 60 % of the administered activity. Samples of sweat of different cutaneous regions were obtained, the maximum values of the activity measured reached 200 Bq/cm 2 . According to the obtained results it is important to elaborate guides to be given to patients as an instrument to reduce the external exposure and to avoid internal contamination. (author)

Therapeutic efficacy of intralesional 131I-labelled hyaluronectin in grafted human glioblastoma

Energy Technology Data Exchange (ETDEWEB)

Girard, N.; Courel, M.N.; Vera, P.; Delpech, B. [Centre Henri-Becquerel, Rouen (France). Laboratoire d' Oncologie Moleculaire

2000-07-01

The grafted human glioblastoma cell CB109 was used as a model for intralesional therapy with 131I-labelled hyaluronectin glycoprotein (131I-HN). 131I-HN bound specifically to in situ hyaluronic acid (HA), a main component of the extracellular matrix which is involved in tumour invasion. Labelling experimental conditions were determined and, finally, 25 {mu}Ci/{mu}gHN, 1 {mu}g chloramine-T/{mu}gHN and a 60-s stirring period provided a 131I-HN preparation with an optimal affinity for HA (64% compared to unlabelled HN). Following intratumoral injection, 131I-HN was retained with a limited diffusion outside the tumour. On day 4 the radioactivity concentrated in the tumour was still 25 times greater than that in the liver, spleen and kidneys combined. For therapeutic assays, 65 {mu}Ci 131I-HN was injected into the tumour, resulting in a delivery of 6.8 Gy over a 7-day period. Controls received unlabelled HN, heat-inactivated HN, a mixture of inactivated HN plus free 131I or no treatment (six animals per group). Tumour volumes were evaluated every second day from treatment day and the rate of tumour growth was expressed as a ratio of tumour size at time intervals to the tumour size at the time of injection. Growth curves were compared: heat-inactivated with or without free 131I had no anti-tumour effect. Unlabelled HN-injected tumours had a slightly slower growth rate than untreated tumours (p < 0.02) and growth rate of 131I-HN-injected tumours was much lower (p < 0.00002). A pronounced inhibitory effect with intralesional 131I-labelled HN injection resulted from a combination of a) blockage of HA, a proliferation facilitating factor, and b) local irradiation of tumoral tissue, while uptake in normal tissues was minimized.

Therapeutic efficacy of intralesional 131I-labelled hyaluronectin in grafted human glioblastoma

International Nuclear Information System (INIS)

Girard, N.; Courel, M.N.; Vera, P.; Delpech, B.

2000-01-01

The grafted human glioblastoma cell CB109 was used as a model for intralesional therapy with 131I-labelled hyaluronectin glycoprotein (131I-HN). 131I-HN bound specifically to in situ hyaluronic acid (HA), a main component of the extracellular matrix which is involved in tumour invasion. Labelling experimental conditions were determined and, finally, 25 μCi/μgHN, 1 μg chloramine-T/μgHN and a 60-s stirring period provided a 131I-HN preparation with an optimal affinity for HA (64% compared to unlabelled HN). Following intratumoral injection, 131I-HN was retained with a limited diffusion outside the tumour. On day 4 the radioactivity concentrated in the tumour was still 25 times greater than that in the liver, spleen and kidneys combined. For therapeutic assays, 65 μCi 131I-HN was injected into the tumour, resulting in a delivery of 6.8 Gy over a 7-day period. Controls received unlabelled HN, heat-inactivated HN, a mixture of inactivated HN plus free 131I or no treatment (six animals per group). Tumour volumes were evaluated every second day from treatment day and the rate of tumour growth was expressed as a ratio of tumour size at time intervals to the tumour size at the time of injection. Growth curves were compared: heat-inactivated with or without free 131I had no anti-tumour effect. Unlabelled HN-injected tumours had a slightly slower growth rate than untreated tumours (p < 0.02) and growth rate of 131I-HN-injected tumours was much lower (p < 0.00002). A pronounced inhibitory effect with intralesional 131I-labelled HN injection resulted from a combination of a) blockage of HA, a proliferation facilitating factor, and b) local irradiation of tumoral tissue, while uptake in normal tissues was minimized

Selection of chemotherapy for metastatic mammary cancer by effect on 131Cs uptake

International Nuclear Information System (INIS)

Ferguson, D.J.; Harper, P.V.

1977-01-01

Cesium-131 was administered intravenously to 39 patients with superficial metastases of mammary carcinoma and the concentration in tumor was compared with that in normal tissue by application of a detector in vivo, before and after 1 to 5 days of chemotherapy with cyclophosphamide (CP), 5-fluorouracil (FU), or diethylstilbestrol. A change of the cesium concentration ratio (tumor/normal issue) greater than 15% after brief treatment correctly predicted the therapeutic effect after 1 to 39 months on the tumors that were tested in 30 of 33 tests. No reliable correlation could be made in the remaining 21 tests in which the change of ratio was less than 15%. The concentration of cesium-131 in the skin, fat, and skeletal muscle of mice was not appreciably altered by treatment for 5 days with CP or FU

Radioisotope-powered photovoltaic generator

International Nuclear Information System (INIS)

McKlveen, J.W.; Uselman, J.

1979-01-01

Disposing of radioactive wastes from nuclear power plants has become one of the most important issues facing the nuclear industry. In a new concept, called a radioisotope photovoltaic generator, a portion of this waste would be used in conjunction with a scintillation material to produce light, with subsequent conversion into electricity via photovoltaic cells. Three types of scintillators and two types of silicon cells were tested in six combinations using 32 P as the radioisotope. The highest system efficiency, determined to be 0.5% when the light intensity was normalized to 100 mW/cm 2 , was obtained using a CsI crystal scintillator and a Helios photovoltaic cell

Radioisotope production in fusion reactors

International Nuclear Information System (INIS)

Engholm, B.A.; Cheng, E.T.; Schultz, K.R.

1986-01-01

Radioisotope production in fusion reactors is being investigated as part of the Fusion Applications and Market Evaluation (FAME) study. /sup 60/Co is the most promising such product identified to date, since the /sup 60/Co demand for medical and food sterilization is strong and the potential output from a fusion reactor is high. Some of the other radioisotopes considered are /sup 99/Tc, /sup 131/l, several Eu isotopes, and /sup 210/Po. Among the stable isotopes of interest are /sup 197/Au, /sup 103/Rh and Os. In all cases, heat or electricity can be co-produced from the fusion reactor, with overall attractive economics

Therapeutic applications of radioactive 131iodine: Procedures and incidents with capsules

International Nuclear Information System (INIS)

Al Aamri, Marwa; Ravichandran, Ramamoorthy; Binukumar, John Pichy; Al Balushi, Naima

2016-01-01

Treatments for thyrotoxicosis and carcinoma thyroid are carried out by oral administration of radioactive iodine ( 131 I) in the form of liquid or capsules. The liquid form of 131 I has higher risk factors such as vapourization, spillage and need for management of higher activity wastes. Use of 131 I in capsule form simplify procedures of handling compared to liquid form of 131 I. The guidelines of safe handling and quality assurance aspects for therapeutic use 131 I are well outlined by International Atomic Energy Agency (IAEA) reports. A few unusual incidents with I-131 capsules encountered in the past need to be highlighted from health physics point of view. In Royal Hospital, Oman, I-131 is imported in capsules, and the total activity handled/year steadily increased over 10 years. Discrete activities range from 185 MBq (5 mCi) up to 7.4 GBq (200 mCi). In four incidents deviations in standard operational procedures were recorded. Nature of incidents is described as follows: (1) After assay of activity, the capsule was directly put in the lead container with missing of inner cap. (2) Patient poured water in the Perspex tube, when the capsule was handed over to her, making an emergency situation. (3) In 3 high activity capsules (2 nos 2.96 GBq, 1 no. 4.26 GBq), observed sticky behavior in capsule holder on the 2 nd day post receipt, which were in order on the 1 st day. (4) A capsule could not be swallowed by a patient, which was taken back from the mouth. Monitoring of patient later did not show residual ingested activity. The report documents some of the unusual incidents for information to other centers engaged in such radioactive administrations

Evaluation of 131I retention in several adsorbers

International Nuclear Information System (INIS)

Catanoso, Marcela F.; Osso Junior, Joao Alberto

2011-01-01

Several iodine radioisotopes are used in nuclear medicine for treatment and diagnostic purposes. The radioisotope 131 I is used both in diagnosis and therapy due to its physical characteristics of decay by β - and its γ-ray emissions suitable for diagnosis. It is routinely produced at IPEN through the irradiation of TeO 2 targets in the IEA-R1m nuclear reactor. After the irradiation, the 131 I is separated by dry distillation, where the targets are put in an oven, heated at 760 deg C for 2 hours and the 131 I, volatile, is carried by an O 2 gas stream. The aim of this work was to evaluate the retention and elution of 131 I samples produced at IPEN in several adsorbers as part of a project aiming the purification of these radioisotopes, allowing the labeling of biomolecules. Samples of 131 I were used for retention and elution studies with the following adsorbers: commercial cartridges, anionic resin columns and cationic resin column. The results showed that Ag cartridges and anionic resins Dowex 1X8, Dowex 3 and IRA 400 had a great iodine retention but no elution after using specific eluents. The QMA light, acid alumina, neutral alumina and cationic resin Dowex 50WX4 showed high retention and elution and QMA plus and cationic resin Dowex 50WX8 and Dowex 50WX12 had a good retention but lower elution. Regarding to the better retention and elution, Ag cartridges and resins showed a higher percentage of iodine retention but lower elution yield and QMA light, acid and neutral alumina cartridges showed better results. (author)

Value of 201Tl imaging in predicting therapeutic 131I uptake in patients with thyroglobulin-positive but 131I scan-negative differentiated thyroid carcinoma

International Nuclear Information System (INIS)

Conlu, R.A.O.; Obaldo, J.M.

2004-01-01

Background: Serum thyroglobulin assay and 131Iodine (1311) whole body scan are considered complementary in detecting malignant thyroid tissue or metastases. A large number of patients, however, are encountered presenting with scan-negative, thyroglobulin-positive differentiated thyroid carcinoma posing a dilemma in therapeutic management. One of the first alternative scanning agents to be employed is 201Thallium (201Tl). Recent studies have demonstrated its usefulness in identifying lesions that are not visualized with traditional 131I whole body scan. It is not clear, however, whether 201Tl scan helps in the decision-making for subsequent 131I therapy. This study was conducted to determine if 201Tl scan can predict therapeutic 131I uptake and to define the clinical role of 201Tl scanning in these patients. Methods and results: A total of 12 patients (20-63 y/o), 5 males and 7 females, underwent surgery for differentiated thyroid cancer and all had serum thyroglobulin values above 10 ng/ml and normal TPO autoantibodies. Pre-therapy 131I scan using 111 MBq (3mCi) of 131I were obtained. As required for inclusion, all patients had negative pre-therapy scan and negative TPO autoantibody results and underwent 20lTl scanning within 3 weeks. All patients were given 131I therapy (3.7-5.5 GBq or 100-150 mCi) between one to two months after 201Tl scanning. Within a week after therapy, all patients underwent whole body 1311 scanning. 201Tl imaging demonstrated thyroid remnants in 9 out of 12 patients having positive 201Tl scan but negative pre-therapy 1311 scan. However, only 2 of the positive 201Tl scans showed 131I uptake post-therapy (positive predictive value of 20%). None of the subjects presented with a negative 201Tl scan and a positive post-therapy 131I scan. Conclusion: Our study suggests that evidence of remnants or metastases on 201Tl scanning may be an inappropriate basis for the decision to proceed with 131I therapy. The role of 20lTl imaging in this subset of

The observation of the therapeutic effectiveness of 131I on 260 youngster with Grave's hyperthyroidism

International Nuclear Information System (INIS)

Liu Binwen; Gao Xiusheng; Zhang Yahua; Pu Dongli

2003-01-01

Objective: To study the therapeutic effect and find new ways on treatment of Grave's hyperthyroidism in youngsters. Methods: 260 Grave's hyperthyroidism patients (age under 21 years) treated with 131 I were followed up 1-16 years later. Results: 118 of all patients were cured and 55 cases improved, failed treatment 2 cases, subclinical hypothyroidism 9 cases, clinical hypothyroidism 6 cases. 35 cases were treated with 131 I two or three times. All the patients with subclinical hypothyroidism and clinical hypothyroidism caused by 131 I were cured with medicine. 131 I treatment had no effect on growth and mentality and didn't cause leukemia nor thyroid cancer. Conclusions: The therapy of youngsters with Grave's hyperthyroidism with 131 I has the same effectiveness as adult. To the youngster Grave's patients who failed medical treatment, therapy with 131 I is safe and effective. It leads to temporary hypothyroidism which can be cured with medicine, no delayed hypothyroidism has been found

The therapeutic threesome, Iodine 131, Lutetium-111 and Rhenium-188 Radionuclide Trifecta

International Nuclear Information System (INIS)

Turner, J.H.

2007-01-01

Full text: Affordable, available, cost-effective, safe, efficacious therapeutic radiopharmaceuticals are required for clinical application throughout the world. In-house preparation of non-proprietary therapeutic radiopharmaceuticals at tertiary referral hospitals in all countries following appropriate technology transfer and training at key research and development centres can potentially supply this need. Illustrative examples of novel therapeutic radiopharmaceuticals currently under development in physician sponsored phase II clinical trials and candidates for contemplation of translation to developing countries include: (1) I-131 Rituximab radioimmunotherapy of relapsed/refractory and first-line treatment of non- Hodgkin's lymphoma; (2) Lu-177 octreotate radiopeptide therapy of neuroendocrine malignancy with capecitabine tumour radiosensitization; (3) Re-188 lipiodol intrahepatic arterial therapy of hepatocellular carcinoma. In addition to presentation of preliminary clinical results, the logistics and techniques of preparation, quality control and administration of each of these therapeutic radiopharmaceuticals will be described and the calculation of individual patient dosimetry and issues of radiation safety will also be addressed. 1. Iodine-131 rituximab: I-131 rituximab may be prepared in a hospital department of nuclear medicine equipped with a shielded fume cupboard, using commercially available single-use sterile pyrogen-free labelling kits (Go Medical Industries Pty Ltd, Subiaco, Australia) (1). Individualized prospective dosimetry is performed on each patient by quantitative whole body gamma imaging, to determine the therapeutic administered activity, to provide a maximum safe whole body radiation absorbed dose of 0.75 Gy, which equates to less than 2 Gy to red marrow (2). More than 200 patients with relapsed/refractory non-Hodgkin's lymphoma have been treated at Fremantle Hospital without infection or haemorrhagic incident. Myelosuppression is self

Preliminary study of 7Be, 137Cs and 131I activity concentration distribution rule in Beijing aerosol

International Nuclear Information System (INIS)

Fan Yuanqing; Wang Shilian; Zhang Xinjun; Li Qi; Jia Huaimao; Zhao Yungang; Chen Zhanying; Chang Yinzhong; Liu Shujiang; Li Huijuan

2013-01-01

The process of aerosol sampling and measuring of Beijing Radionuclide Station and Beijing Radionuclide Laboratory of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) International Monitoring System (IMS) was described. Long time aerosol monitoring data of the station and the laboratory were analyzed through statistic method and the characteristic and rule of the concentration distribution of nuclides 7 Be, 137 Cs and 131 I were obtained. The foundation was formed for further studying the rule of the radionuclide distribution in atmosphere. (authors)

Testing CAN/CSA-N288.1-M87 (Air-to-forage-to-milk or -beef pathways for 131I and 137Cs and the water-to-fish and sediment pathways for 137Cs) against post-Chernobyl observations

International Nuclear Information System (INIS)

Peterson, S-R.

1993-05-01

The Canadian Standards Association's 'Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities' (CAN/CSA-N288.1-M87) is a steady-state chronic release model. Although it has been assumed that (because dose calculations involve several steps and because each step has some degree of conservatism) predictions usually should be conservative, the model had not been tested. An opportunity to test the model arose due to the activities of BIOMOVS (Biospheric Model Validation Study), which developed several scenarios with which to assess model performance. Each of these scenarios asked for predictions for several steps in the pathways studied (e.g., deposition, concentrations in forage and concentrations in milk or meat). The first of these, Scenario B1, was a chronic release over 30 years of 131 I and 137 Cs; predictions of CSA-N288.1-M87 have been compared with those of the sixteen models participating in the scenario. Scenario A4 was developed using world-wide 131 I and 137 Cs data from the Chernobyl accident, and from the following six months. Predictions made using CSA-N288.1-M87 were compared with observations. In addition, the results were compared with those of the 25 participating models. Finally, the model was used to calculate 137 Cs concentrations in water, sediment and fish in a Swedish lake for 18 months post-Chernobyl, for comparison with observations and other predictions. As assumed, most of the transfer parameters are conservative, so that the predictions are usually conservative for a source term of atmospheric 131 I. However, estimates of deposition for both 131 I and 137 Cs are not conservative, which has profound implications for estimating external dose. Furthermore, at some of the sites in the A4 Scenario, concentrations in milk and beef are underestimated for 137C s, which suggests that the transfer parameters are not as conservative as might be desired

SU-F-T-653: Radiation Exposure from Cs-131 Permanent Seed Implants

Energy Technology Data Exchange (ETDEWEB)

Giaddui, T; Hardin, M; To, D; Kremmel, E; Peng, C; Hann, P; Richardson, S; Yu, Y; Harrison, A; Doyle, L [Sidney Kimmel Cancer Center, Thomas Jefferson University, Philadelphia, PA (United States)

2016-06-15

Purpose: Permanent seed implants have traditionally been used to treat prostate, lung and head or neck cancers using I-125 and Pd-103. Cs-131, which has higher dose rate is being used to treat brain, head and/or neck cancers in our clinic, therefore, we chose to monitor the dose received by surgeons during the extensive procedure. The aims of this work are to assess the level of radiation exposure to surgeons and the instantaneous exposure at bedside and 1 m from patients. Methods: Ten patients received Cs-131 implants for recurrent brain,head and/or neck cancer; the median implanted activity, number of implanted seeds and prescription dose at 0.5 cm from the perpendicular plane of the implant were: 54.3 mCi (14.52 – 77); 19 (4 – 24) and 60 Gy (range 42 – 60) respectively. Radiation exposure was recorded at bedside and 1 m from the patient using Victoreen ion chamber (Fluke Biomedical, Cleveland, OH). Exposure to surgeons was measured using TLD (Mirion Technologies (GDS), Inc., USA). Results: The median equivalent dose rate at 1 m and bedside immediately following implantation were 1.49×10-2 mSv/h (8.77×10-3–2.63×10-2) and 7.76×10-2 mSv/h (3.1×10-2– 1.53×10-1) respectively. Median equivalent dose to surgeons’ hands was 0.60 mSv (0.33 – 1.48) and no doses were detected for whole-body. Surgical reconstruction for one patient was performed 71 days post-implant and resulted in zero exposure to surgeons. Conclusion: The recorded exposure rates were low when compared with the literature. Post procedure surveys at bed site and 1 m indicated that all patients were within safe limits for discharge (< 0.05 mSv/h at 1 m). However, as a precautionary measure, patients were advised to avoid direct contact with children and pregnant women within four weeks of the implant and stay at least at 3 ft from other people. Surgeons doses were well within occupational dose limits.

Study of the therapeutic dose and the clinical effect on Graves' disease with I-131 treatment

International Nuclear Information System (INIS)

Dang, Y.

2005-01-01

Full text: Graves' disease is being treated with I-131 for more than 40 years in China. Previously the dose of I-131 used to be calculated using the 'Quimby' formula. We have now observed that the dose of I-131 administered to patients is now lower in recent years than the early years. The radioactive iodine uptake by the thyroid gland has also changed significantly over a period of time. In this paper we intend to explore these reasons and to research the relationship between the dose and the effect as well as the main cause of the incidence of the hypothyroidism. The parameters in 'Quimby' formula including I-131 uptake, effective half-life and thyroid weight were analyzed and compared with each year data from 1961 to 1988 and subjected to multiple regression analysis to determine the influence on the calculation of dose in 4465 patients. The therapeutic effects were compared with the data of the clinical follow-up of patients between 1961-1973 and 1978-1988 in 748 patients. The factors which might lead to the hypothyroidism were investigated with the non-condition logistic regression. The I-131 uptake was repeatedly measured within one week in 100 patients to identify the changing pattern of the I-131 uptake and its influence on the administered therapeutic dose. We observed an increase in the value of I-131 uptake. The value of I-131 uptake showed an increase after 1977, as well as a prolongation of effective half-life after 1973. The main reason for these changes being a replacement of the equipment in 1977 (G-M counter tube was replaced by scintillation counter), and the other reason being salt iodization in China in 1973. These two factors resulted in a significant reduction in the administered dose of I-131 during the period 1974-1988 as compared to the previous period 1961-1973; the mean administered doses being 168.35MBq and 330.33MBq respectively. The result of multiple regression analyses suggested that the thyroid weight and the effective half

Possibilities and limitations of information in radioisotope examination of liver function

International Nuclear Information System (INIS)

Blaha, V.; Kolinska, J.; Horak, J.

1985-01-01

The 20 years' experience is described with the use of clearance methods for radiocolloid - 198 Au, Rose Bengal- 131 I and the extraction fraction of Rose Bengal- 131 I in patients with different liver disorders. Attention is also focused on indications, interpretations, as well as on the advantages and information limits of the above-mentioned radioisotope methods. (author)

Radioisotope production at PUSPATI - five year programme

International Nuclear Information System (INIS)

Yusof Azuddin Ali; Abdul Rahman Mohamad Ali.

1983-01-01

Most of the basic laboratory facilities for radioisotopes production at PUSPATI will be commissioned by September 1983. Work on setting up of production and dispensing facilities is in progress as the nuclides being worked on are those that are commonly used in medical applications, such as Tc-99m, I-131, P-32 and other nuclides such as Na-24 and K-42. Kits for compounds labelled with Tc-99m such as Stannous Pyrophosphate, Sulfur Colloid and Stannous Glucoheptonate are being prepared. The irradiation facilities available now for radioisotope production at the PUSPATI TRIGA Reactor include a central thimble (flux density 1 x 10 13 n.cm -2 S -1 ) and a rotary specimen rack (flux density 0.2 x 10 13 n.cm -1 S -1 ). Irradiation schedules and target handling techniqes are discussed. Plans for radioisotope production at PUSPATI over the period of 1983-1987, based on present demand for radioisotope, are also explained. (author)

Evaluation of {sup 131}I retention in several adsorbers

Energy Technology Data Exchange (ETDEWEB)

Catanoso, Marcela F.; Osso Junior, Joao Alberto, E-mail: marcela.forli@gmail.co, E-mail: jaosso@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Diretoria de Radiofarmacia

2011-07-01

Several iodine radioisotopes are used in nuclear medicine for treatment and diagnostic purposes. The radioisotope {sup 131}I is used both in diagnosis and therapy due to its physical characteristics of decay by {beta}{sup -} and its {gamma}-ray emissions suitable for diagnosis. It is routinely produced at IPEN through the irradiation of TeO{sub 2} targets in the IEA-R1m nuclear reactor. After the irradiation, the {sup 131}I is separated by dry distillation, where the targets are put in an oven, heated at 760 deg C for 2 hours and the {sup 131}I, volatile, is carried by an O{sub 2} gas stream. The aim of this work was to evaluate the retention and elution of {sup 131}I samples produced at IPEN in several adsorbers as part of a project aiming the purification of these radioisotopes, allowing the labeling of biomolecules. Samples of {sup 131}I were used for retention and elution studies with the following adsorbers: commercial cartridges, anionic resin columns and cationic resin column. The results showed that Ag cartridges and anionic resins Dowex 1X8, Dowex 3 and IRA 400 had a great iodine retention but no elution after using specific eluents. The QMA light, acid alumina, neutral alumina and cationic resin Dowex 50WX4 showed high retention and elution and QMA plus and cationic resin Dowex 50WX8 and Dowex 50WX12 had a good retention but lower elution. Regarding to the better retention and elution, Ag cartridges and resins showed a higher percentage of iodine retention but lower elution yield and QMA light, acid and neutral alumina cartridges showed better results. (author)

High radio-isotope uptakes in patients with hypothyroidism

Energy Technology Data Exchange (ETDEWEB)

Wing, J.; Kalk, W.J.; Ganda, C. (University of the Witwatersrand, Johannesburg (South Africa). Dept. of Medicine)

1982-12-04

Hypothyroidism is usually associated with a low radio-isotope uptake by the thyriod gland. We report 8 cases of Hashimoto's thyroiditis with clinical and biochemical hypothyroidism and with borderline high or overtly increased technetium-99m pertechnetate and/or iodine-131 uptakes.

Economic Contributions of Radioisotope Production Reactor in Korea

International Nuclear Information System (INIS)

Nam, Ji Hee; Kim, Seung Su; Moon, Kee Whan

2010-01-01

Radioisotopes (RIs) have been used extensively in the fields of industrial, the agricultural, and the medical applications. Especially the deficiency of radioisotopes such as Mo-99 and I-131 in the medical applications recently is becoming the main issue in our society. Radioisotope with the characteristics of public goods in some aspects is mainly playing as the intermediate inputs or goods in the process of the industrial production, with being expected to produce the economic benefits by creating the new demand in the market or enlarging the value added for the related goods and services. In this study, the contribution effects for Korean economy by the construction and operation of the reactor for radioisotope production would be evaluated the effects produced by the activities such as a RI supplies into domestic industry, the RI exports, the neutron transmutation doping services called NTD, and the exports of RI production reactors

A comparison of the radiochemical stability of different iodine-131 labelled metaiodobenzylguanidine formulations for therapeutic use

International Nuclear Information System (INIS)

Wafelman, A.R.; Beijnen, J.H.; Hoefnagel, C.A.; Maes, R.A.A.

1994-01-01

The results of a stability study of three commercially available formulations of [ 131 I]MIBG for therapeutic use and an unstabilized formulation, stored under various conditions, are presented. The stability was followed for 20 days. In all formulations tested, free [ 131 I]iodide, formed by radiolysis, was the most important radiochemical impurity. The pharmaceutical formulation with the largest amount of stabilizer was radiochemically - but not chemically -most stable. (author)

Summary report of the consultants' meeting on nuclear data for production of therapeutic radioisotopes

International Nuclear Information System (INIS)

Haight, R.C.; Paviotti-Corcuera, R.

2002-04-01

This report summarizes the presentations, recommendations and conclusions of the Consultants' Meeting on Nuclear Data for Production of Therapeutic Radioisotopes. The purpose of this meeting was to discuss scientific and technical matters related to the subject and to advise the IAEA Nuclear Data Section (NDS) on the need and possible formation of a Coordinated Research Programme (CRP). Accurate and complete knowledge of nuclear data are essential for the production of radionuclides for therapy to achieve the specific activity and purity required for efficient and safe clinical application. The Consultants recommended updating and completing the data for production of radionuclides that are recognized to be important in therapy. In addition, the consultants recommend investigating other radionuclides that have a potential interest and for which there exists a medical rationale for therapeutic use. To date no serious effort has been devoted to evaluation of nuclear data for the reactor and accelerator production of therapeutic radionuclides. The IAEA is in the unique and privileged position to address this important public health related problem. Therefore, the consultants highly recommend the formation of a CRP with the title: 'Nuclear Data for Production of Therapeutic Radionuclides.' (author)

Hair radioactivity as a measure of exposure to radioisotopes

Science.gov (United States)

Strain, W. H.; Pories, W. J.; Fratianne, R. B.; Flynn, A.

1972-01-01

Since many radioisotopes accumulate in hair, this tropism was investigated by comparing the radioactivity of shaved with plucked hair collected from rats at various time intervals up to 24 hrs after intravenous injection of the ecologically important radioisotopes, iodine-131, manganese-54, strontium-85, and zinc-65. The plucked hair includes the hair follicles where biochemical transformations are taking place. The data indicate a slight surge of each radioisotpe into the hair immediately after injection, a variation of content of each radionuclide in the hair, and a greater accumulation of radioactivity in plucked than in shaved hair. These results have application not only to hair as a measure of exposure to radioisotopes, but also to tissue damage and repair at the hair follicle.

Elementary concepts of the radioisotopes uses

International Nuclear Information System (INIS)

Pisarev, Mario A.

2004-01-01

Endocrinology has been one of the specialties earlier benefited for the radioisotopes uses in the diagnosis and treatment of different affections. These applications are based on the radioisotopes property of biochemical behaving as non- radioactive molecules, and at the same time, radiations emitting that can be detected by suitable means (diagnostic utility) or that have effects on biological systems (therapeutic action). (author) [es

Comparative Analysis of Direct and Indirect 131I Measurement Methods from the Stack to Outdoor

Directory of Open Access Journals (Sweden)

G. Suhariyono

2017-11-01

Full Text Available The radioisotope production facility at PUSPIPTEK Serpong produces and processes 131I that can disperse to the settlements (community and the environment around the Serpong Nuclear Area (SNA. 131I is produced routinely for medical uses in hospitals and pharmacies, for both domestic uses and export. 131I is a beta and gamma emitting radioactive material and can cause thyroid cancer. The problem was that there was so far no research and in-depth assessment of the aerial dispersion of 131I radioactivity emitted from the radioisotope production stack to the environment at actual conditions. The research was conducted through simultaneous measurement of 131I radioactivity in the stack of the 131I radioisotope production facility, Serpong, and outdoor in house courtyards around SNA in normal condition (no accident based on the variations of the distance and wind direction. Direct measurements were carried out with a portable in-situ NaI(Tl detector at outdoor, and with a LaBr3 detector in the stack. Indirect measurements were carried out by using charcoal filter and vacuum pump in the stack and outdoor. The direct measurement method has many advantages over the indirect measurement. The direct measurement method was found to be more accurate, less expensive, easier to operate, needing just one operator in its implementation, portable, and can be operated continuously and for long durations. The overall activity concentrations of 131I on average obtained by either direct or indirect method were still below the upper limit of 131I activity concentration in the air (530 Bq/m3 stipulated by the Regulation of the Chairman of BAPETEN (Perka BAPETEN No. 7/2013. 

Studies of 131I, 137Cs and 103Ru in milk, meat and vegetables in North East Scotland following the Chernobyl accident

International Nuclear Information System (INIS)

Martin, C.J.; Heaton, B.; Robb, J.D.

1988-01-01

Uptake and clearance of radionuclides in foodstuffs have been studied in the neighbourhood of Aberdeen in North East Scotland following the Chernobyl accident. The level of 131 I in goats' milk was 100-200 Bq litre -1 in early May and declined with an effective half-life of 4.3 days, but that in cows's milk was only a few Bq litre -1 as most cattle were kept indoors. 137 Cs and 103 Ru activities in broccoli declined with effective half-lives of 11 and 6 days respectively, while 137 Cs in grass decreased with a half-life of 22 days, the reduction appearing to show a relationship to weekly rainfall. Studies of tissues from groups of lambs initially grazed on contaminated pasture and later (a) fed indoors on concentrates or (b) continuing to graze outdoors, showed the 137 Cs concentrations to decline with half-lives of (a) 17 days and (b) 25 days, while the half-lives describing the reduction in total 137 Cs activity were (a) 20 days and (b) 35 days. (author)

Radiation surveillance procedure during veterinary application of radioisotope

International Nuclear Information System (INIS)

Kamaldeep; Bhaktivinayagam, A.; Singh, Sanjay Kumar

2012-01-01

Radioisotopes have found wide applications in the field of biomedical veterinary nuclear medicine and research. Radiation safety issues during internal administration of radioisotopes to laboratory animals, unlike human use, are far more challenging and requires stringent, well planned and an organized system of radiation protection in the animal house facility. In this paper, we discuss our experience during veterinary research experiments involving use, handling and administration of liquid sources of 131 I. With extensive radiation protection surveillance and application of practical and essential radiation safety and hygiene practices, the radiation exposure and contamination levels during the veterinary application of isotopes can be kept ALARA

Multiple model testing using Chernobyl fallout data of I-131 in forage and milk and Cs-137 in forage, milk, beef and grain. Pt. 1

International Nuclear Information System (INIS)

Koehler, H.; Peterson, S.R.; Owen Hoffman, F.

1991-03-01

Comprehensive measurements of I-131 and Cs-137 in the environment after the Chernobyl accident provided a unique opportunity for the collection of environmental transfer data sets. These come from 13 locations in the northern hemisphere which experienced levels of contamination that spanned approximately three orders of magnitude. Data have been compiled for radionuclide concentrations in air, rain, pasture vegetation, milk, beef and grain. In addition background information has been collated for factors such as prevailing meteorological conditions, location description, and local agricultural practices. Participants were asked to predict radionuclide concentrations in forage, milk, beef and grain from radionuclide concentrations in air, the daily amounts of precipitation and other pertinent information. This was a blind test in that the locations to which the input data referred were not revealed to the participants until after they had submitted their predictions. Twenty-three models were involved in the study. This report compares observations and predictions for deposition, time- integrated concentrations in forage, milk, beef and grain, to help assess understanding of individual processes, time-dependent concentrations in forage, milk and beef. In general, predictions of time-integrated concentration of I-131 and Cs-137 in forage, milk (normalized for forage) and beef are within a factor of 10 of the observations. About 50% of the predictions of I-131 and Cs-137 in forage and just over 30% of the predictions of those nuclides in milk (normalized for forage) fall within a factor of 2 of the observations. Documentation of the measurements, models, methods of analysis and model results is presented in the appendices. (au) (75 refs.)

Measurement and interpretation of nuclear properties of the 95Mo, 115In e 131Cs

International Nuclear Information System (INIS)

Maciel, A.

1970-01-01

Nuclear properties through the measurement of angular correlations of gamma-gamma cascades, with and without magnetic field, is experimentally investigated. The equipment used is basically a fast-slow coincidence system which includes a multichannel analyser and two detectors. An essential aspect of the set-up is the use of Ge(Li) and Si(Li) detectors. The three nuclei studied are: 95 Mo, 115 In and 131 Cs. For each of the first two, the magnetic moment of one excited state is determined and for the last two it is possible to assign spins to some levels and multipolarities to various radiations. A theoretical analysis for each of these isotopes is performed in terms of nuclear models. In the case of 95 Mo a more detailed study of a special coupling model is made [pt

Late biological effects of 137CsCl injected in beagle dogs

International Nuclear Information System (INIS)

Nikula, K.J.; Muggenburg, B.A.; Griffith, W.C.; Hahn, F.F.; Boecker, B.B.

1994-01-01

The toxicity of intravenously administered 137 CsCl in the Beagle dog was investigated as part of the ITRI program to evaluate the biological effects of internally deposited fission product radionuclides. The toxicity and health effects of 137 Cs are important to understand because 137 Cs is produced in large amounts in light-water nuclear reactors. Also, large quantities of cesium radioisotopes have entered the human food chain as a result of atmospheric nuclear weapons tests and additonal cesium radioisotopes were released during the Chernobyl accident. The intravenous route of exposure was chosen because it was known that after intravenous injection, inhalation, or ingestion, internally deposited 137 CsCl is rapidly adsorbed and distributed throughout the body, exposing the whole body to beta and gamma radiation, and because of the reduced radiation protection problems associated with high-level exposure via injection compared to these other routes

Manual of radioisotope production

International Nuclear Information System (INIS)

1966-01-01

The Manual of Radioisotope Production has been compiled primarily to help small reactor establishments which need a modest programme of radioisotope production for local requirements. It is not comprehensive, but gives guidance on essential preliminary considerations and problems that may be met in the early stages of production. References are included as an aid to the reader who wishes to seek further in the extensive literature on the subject. In preparing the Manual, which is in two parts, the Agency consulted several Member States which already have long experience in radioisotope production. An attempt has been made to condense this experience, firstly, by setting out the technical and economic considerations which govern the planning and execution of an isotope programme and, secondly, by providing experimental details of isotope production processes. Part I covers topics common to all radioisotope processing, namely, laboratory design, handling and dispensing of radioactive solutions, quality control, measurement and radiological safety. Part II contains information on the fifteen radioisotopes in most common use. These are bromine-82, cobalt-58, chromium-51, copper-64, fluorine-18, gold-198, iodine-131, iron-59, magnesium-28, potassium-42, sodium-24, phosphorus-32, sulphur-35, yttrium-90 and zinc-65. Their nuclear properties are described, references to typical applications are given and published methods of production are reviewed; also included are descriptions in detail of the production processes used at several national atomic energy organizations. No attempt has been made to distinguish the best values for nuclear data or to comment on the relative merits of production processes. Each process is presented essentially as it was described by the contributor on the understanding that critical comparisons are not necessary for processes which have been well tried in practical production for many years. The information is presented as a guide to enable

Risk of internal contamination of workers employed in radioisotope laboratories in Poland

Energy Technology Data Exchange (ETDEWEB)

Adamiak-Ziemba, J.; Domanski, T.; Doniec, J.

1981-01-01

It was established that in Poland 247 radioisotope laboratories use open radiation sources. These laboratories have not yet been covered by the internal system of control of inner contamination. The number of workers having contact with radioisotopes amounts to 1987. Frequently this is work in contact with several radioisotopes (from 1 to 17). Most workers are exposed to tritium (over 500 workers), /sup 14/C (over 500), /sup 125/I and /sup 131/I, /sup 32/P, /sup 51/Cr, 99mTc (over 100), isotopes belonging to radiotoxicity groups 2, 3 and 4. In the radiotoxicity group 1 the most workers were exposed to /sup 226/Ra (52).

Manual for reactor produced radioisotopes

International Nuclear Information System (INIS)

2003-01-01

numerous new developments that have taken place since then. Hence in this manual it was decided to focus only on reactor produced radioisotopes. This manual contains procedures for 48 important reactor-produced isotopes. These were contributed by major radioisotope producers from different parts of the world and are based on their practical experience. In case of widely used radioisotopes such as 131 I, 32 P and 99 Mo, information from more than one centre is included so that the users can compare the procedures. As in the earlier two versions, a general introductory write-up is included covering basic information on related aspects such as target irradiation, handling facilities, radiation protection and transportation, but in less detail. Relevant IAEA publications on such matters, particularly related to radiation protection and transportation, should be referred to for guidelines. Similarly, the nuclear data contained in the manual are only indicative and the relevant databases should be referred to for more authentic values. It is hoped that the manual will be a useful source of information for those working in radioisotope production laboratories as well as those intending to initiate such activities

Twenty years of radioisotope production from Institute of Atomic Energy reactors

International Nuclear Information System (INIS)

Lun, Xiao

1980-01-01

The heavy water reactor in People's Republic of China went critical in November, 1958, and the radioisotope development work began since then. The thermal power of the reactor was 7 MW, and the maximum thermal neutron flux was 1.2 x 10 14 n/cm 2 /sec. Since 1967, it was operated at 10 MW. The first radioisotope product was 24 Na, using Na 2 CO 3 as a target, while the first chemically processed product was an electroplated reference source of 60 Co. The first processed radiochemical was the carrier-free H 2 SO 4 of 35 S. Since then, 131 I and 32 P for medical uses, colloidal 198 Au, colloidal Cr 32 PO 4 , chemicals containing 203 Hg, organic compounds labelled with 125 I, 131 I, 3 H and 14 C and smoke detectors have been produced to date. In addition, 22 Na, 54 Mn, 57 Co, 88 Y, 109 Cd have been prepared from a cyclotron. Now about 140 kinds of products can be supplied, and 60% of the users are the hospitals with nuclear medicine department. The present status of the kinds and production figures of nuclear medicines, radiopharmaceuticals, labelled compounds, radiation sources, and some works in progress are reported. General aspects of the application of radioisotopes in China are also described. Radioisotopes have been applied to agriculture, industry, medicine, and sciences such as physics, chemistry, biology and geography. (Wakatsuki, Y.)

Comparative retention of 60Co, 109Cd, and 137Cs following acute and chronic feeding in Bobwhite quail

International Nuclear Information System (INIS)

Anderson, S.H.; Dodson, G.J.; Van Hook, R.I.

1975-01-01

Tissue distribution of the radionuclides were found in the groups given the chronic exposure. Under chronic exposure to 60 Co, 109 Cd, and 137 Cs, quail rapidly accumulated these radioisotopes and the respective body burden concentrations began to level off after 11, 21, and 21 days of exposure. The biological half-lives for radioisotopes accumulated during the chronic feedings were 13 days for 60 Co, 8 days for 109 Cd, and 11 days for 137 Cs. In contrast, biological half-lives for these radioisotopes under acute feeding conditions (single four-hour feeding) were 15 days for 60 Co, 3 days for 109 Cd, and 10 days for 137 Cs. These results indicate that food chain behavior of 60 Co and 137 Cs in Bobwhite is similar following either acute or chronic exposure to contaminated food. For 109 Cd, biological retention in Bobwhite was longer under chronic exposure conditions. (U.S.)

Long-term follow-up study of the therapeutic effect after iodine-131 therapy for hyperthyroidism

International Nuclear Information System (INIS)

Liu Changjiang; Li Long; Gao Jianqing; Xu Sumei; Chen Linna; Zhou Jianming

2006-01-01

To investigate the therapeutic effect through long-term visit and analyze the affecting factors of cure rate after iodine-131 therapy for hyperthyroidism, a long-term follow-up has been undertaken for the patients with hyperthyroidism after iodine-131 treatment. The following results have been obtained. (1) The cure rate of iodine-131 therapy for hyperthyroidism is 74.4%, and the incidence of permanent hypothyroidism is 7.5%. (2) There is no significant difference in the cure rate and incidence of hypothyroidism between the groups of male and female or 'not take ATD' and 'ATD withdrawn longer than 2 weeks' (P>0.05). (3) The difference of the cure rate among the groups of the courses of disease 3 a are significant (P 55 g are significant (P 0.05). The course of disease, age and thyroid mass are the major factors which influence the cure rate. Meanwhile, age and thyroid mass are the major factors which influence the incidence of hypothyroidism. To get high cure rate, the patients with hyperthyroidism should be treated with iodine-131 as early as possible. In the meantime, the incidence of permanent hypothyroidism must be paid attention to. (authors)

The risk of internal contamination of workers employed in radioisotope laboratories in Poland

International Nuclear Information System (INIS)

Adamiak-Ziemba, J.; Domanski, T.; Doniec, J.

1981-01-01

It was established that in Poland 247 radioisotope laboratories use open radiation sources. These laboratories have not yet been covered by the internal system of control of inner contamination. The number of workers having contact with radioisotopes amounts to 1987. Frequently this is work in contact with several radioisotopes (from 1 to 17). Most workers are exposed to tritium (over 500 workers), 14 C (over 500), 125 I and 131 I, 32 P, 51 Cr, 99mTc (over 100), isotopes belonging to radiotoxicity groups 2, 3 and 4. In the radiotoxicity group 1 the most workers were exposed to 226 Ra (52). (author)

An analysis of the dose and the therapeutic effect of 131I in treating youngsters with Graves disease

International Nuclear Information System (INIS)

Li Jia; Qin Lan; Ren Zhong; Zhang Youping

2010-01-01

Objective: To analyses the clinical data of 131 I in treating youngsters with Graves disease, and to explore the effective dose range which is appropriate for Chinese youngsters with Graves disease. Methods: Two hundred and thirty-four youngsters with Graves disease were selected in this study, their ages were between 8 and 17, the average quality of their thyroids was (59.0±16.5)g. According to the absorbed dose of 131 I per gram of thyroid gland, 234 patients were divided into five groups: A: 1.11- 2.59 MBq/g. The therapeutic effect was evaluated by observing after treatment. And calculate the recovery rate, the improvement rate and the incidence rate of hypothyroidism. Results: (1) One hundred and fifty-two (64.95%) patients were cured, 56 (23.93%) were much better than before and 26 (11.11%) were hypothyroid. The therapeutic effect of group B was the best in all groups. (2) The recovery rate: there was no significant difference between group B, group C and group D (χ 2 =2.68, P>0.05). The recovery rate of group B was better than group A and group E (χ 2 =10.20 and χ 2 =5.49, P 2 =1.94, P>0.05). The improvement rate of group A was the highest (χ 2 =8.74, χ 2 =6.68, χ 2 =7.01 and χ 2 =11.12, P 2 =2.71, P>0.05). Group E had the highest incidence rate of hypothyroidism (χ 2 =12.36, χ = 11.58, χ 2 =9.37 and χ 2 =4.36, P 131 I is a safe and effective therapeutic approach for youngsters with Graves disease. We suggest the absorbed dose range of 131 I per gram of thyroid gland is 1.48-2.59 MBq/g, which can obtain the better therapeutic effect and can't increase the incidence rate of hypothyroidism. (authors)

Radioisotope methodology course radioprotection aspects

International Nuclear Information System (INIS)

Bergoc, R.M.; Caro, R.A.; Menossi, C.A.

1996-01-01

The advancement knowledge in molecular and cell biology, biochemistry, medicine and pharmacology, which has taken place during the last 50 years, after World War II finalization, is really outstanding. It can be safely said that this fact is principally due to the application of radioisotope techniques. The research on metabolisms, biodistribution of pharmaceuticals, pharmacodynamics, etc., is mostly carried out by means of techniques employing radioactive materials. Radioisotopes and radiation are frequently used in medicine both as diagnostic and therapeutic tools. The radioimmunoanalysis is today a routine method in endocrinology and in general clinical medicine. The receptor determination and characterization is a steadily growing methodology used in clinical biochemistry, pharmacology and medicine. The use of radiopharmaceuticals and radiation of different origins, for therapeutic purposes, should not be overlooked. For these reasons, the importance to teach radioisotope methodology is steadily growing. This is principally the case for specialization at the post-graduate level but at the pre graduate curriculum it is worthwhile to give some elementary theoretical and practical notions on this subject. These observations are justified by a more than 30 years teaching experience at both levels at the School of Pharmacy and Biochemistry of the University of Buenos Aires, Argentina. In 1960 we began to teach Physics III, an obligatory pregraduate course for biochemistry students, in which some elementary notions of radioactivity and measurement techniques were given. Successive modifications of the biochemistry pregraduate curriculum incorporated radiochemistry as an elective subject and since 1978, radioisotope methodology, as obligatory subject for biochemistry students. This subject is given at the radioisotope laboratory during the first semester of each year and its objective is to provide theoretical and practical knowledge to the biochemistry students, even

Optimization of the therapeutic dose of 131I for thyroid differentiated carcinoma

International Nuclear Information System (INIS)

Lima, Fabiana Farias de

2002-09-01

organs, such as the narrow and gonads, of up to 78.4%.Possible benefits to the institution also include the use of less radioactive material and a reduction in radiation exposures to the staff during the manipulation and administration of the 131 I. To facilitate the calculations of the optimum therapeutic activity of 131 I for individual patients, a simple and fast dose planning program was created (PlanDose). The program has been set up to evaluate thryroid remant ablation, but it can also be used for the calculation of the activity to be administered for treatment of hyperthyroidism. This protocol of calculated optimal patient-specific 131 I. activities allows a better determination of the necessary ablative dose for patients with differentiated carcinoma of the thyroid, and is an example of optimizing the practice of radiation protection. (author)

Predictive capabilities of the specific activity hypothesis for Cs and Zn in freshwater systems

International Nuclear Information System (INIS)

Seelye, J.G.

1975-01-01

Predictions of radioisotope concentrations in components of aquatic systems have been attempted using the specific activity concept, an approach that seems theoretically sound. A comprehensive examination of the specific activities of 134 Cs and 65 Zn in the components of a freshwater system, over a 10 month period, was conducted to evaluate the specific activity hypothesis under applied conditions. This study was designed to provide comparisons of predicted and observed specific activities and to test the equivalence of specific activities between all components of the system. One dose of radioisotopes was added to the system in this study and even after 10 months these radioisotopes were not distributed similarly to the stable isotopes. This suggests that the time necessary to reach a specific activity equilibrium might be a matter of years rather than months. More importantly, in natural systems, where the radioisotope addition is continuous a specific activity equilibrium may never be achieved. These things plus the non-conservative nature of the 134 Cs and 65 Zn predicted concentrations indicates that the use of the specific activity concept for predicting radioisotope concentrations of Cs and Zn in freshwater systems is questionable. A more rigorous approach must be used, considering isotope transfer rates between components and the complexity of the system. Problems with statistical comparisons of derived variables, such as specific activities, are discussed and were considered in interpreting the results of this study

A Survey on the Usage and Demand of Medical Radioisotope and Radiopharmaceuticals in Malaysia

International Nuclear Information System (INIS)

Muhammad Fakhrurazi Ahmad Fadzil; Siti Selina Abdul Hamid; Siti Najila Mohd Janib; Azahari Kasbollah; Syed Asraf Fahlawi Wafa

2016-01-01

Medical radioisotope is a small quantity of radioactive substance used for the purpose of diagnostic and therapy of various diseases. In Malaysia, the emerging of new nuclear medicine centers or institutions in both government and private sectors rose abruptly for the past few years. Currently, there are no data available on the usage and demand of these medical radioisotope or radiopharmaceuticals. The aim of this study is to assess current medical radioisotopes and radiopharmaceuticals usage and also to provide data on current medical radioisotope and radiopharmaceuticals demand for both private and government hospitals or institutions in Malaysia. A survey for a period of 3 months was conducted across Malaysia. The survey was divided into five (5) main parts and it was distributed among health care professionals involved working with medical radioisotope and radiopharmaceuticals in private, government and university based hospitals or institutions and was distributed manually either by hand, mail or e-mail. Data is presented in either pie chart or bar chart. Survey results found out that the highest demand and the highest usage among all radioisotopes are Technetium-99m and radioiodine isotopes such as the iodine-131, iodine-131 MIBG, iodine-123 and iodine-123 MIBG. Technetium-99m is the backbone of nuclear medicine whereby more than 80 % of Nuclear Medicine services utilize this radioisotope. Technetium-99m supply chain is unstable globally and in coming future, two main reactors that produce 60 % of world Molybdenum-99 will shut down and the supply of molybdenum-99 will be disrupted. In radioiodine services, currently, Iodine-123 cannot be obtained in Malaysia and neighboring countries due to its short half-life. Iodine-123 is useful in diagnostic of thyroid related diseases. As for PET services, the highest demands are F-18 FDG and gallium-68 Generator. It is important for Malaysia to self-produced medical radioisotope and radiopharmaceuticals to meet the

Synthesis and labelling of 19-iodocholesterol 131I

International Nuclear Information System (INIS)

Hamada, E.S.

1979-01-01

Considering the increasing interest in obtaining agents for vizualization of the adrenal gland with radioisotopic techniques, 19-iodocholesterol was prepared by means of chemical synthesis and radioiodine ( 131 I) introduced by isotopic exchange reaction. The reaction product was identified by determination of the melting point and elementary spectroscopic analysis (infra-red absorption and magnetic nuclear ressonance). Radiochemical analysis of the labelled compound was performed by means of then-layer cromatography in silica-gel. In order to confirm its capacity of concentration in the adrenal gland, the distribution of 19-iodocholesterol 131 I, after intravenous injection, was tested in rats. (Author) [pt

RSG-Gas Based Radioisotopes And Sharing Program For Regional Back Up Supply

International Nuclear Information System (INIS)

Soenardjo, Sunarhadijoso; Tamat, Swasono R.; Suparman, Ibon; Purwadi, Bambang

2003-01-01

As the owner of the reactors used for radioisotope production, BATAN needs to increase the effectiveness of the reactor operation cost that can be achieved by simultaneously exploiting all the existing irradiation facility, supported by full utilization of the radioisotopes produced. On the other hand, the domestic demand of radioisotopes is much lower than the production capability but sometimes the request is compulsory to be suspended due to reactor operation schedule. As this condition is mostly similar to that of several countries of RCA Member States, a sharing program for regional back up supply seems to be a positive thought to support expectation on the effectiveness of reactor operation cost and the continuity of radioisotope product services as well as the utilization of radioisotopes produced. Based on radioactivity achieved in each production batch at the present, 131 I, 99 Mo, 153 Sm, 125 I and 32 p radioisotopes may be offered for back up supply program. Due to consideration on conformity of user demands with reactor operation and radiochemical processing costs, the concept of back up supply program should performed first by means of full utilization of the available products and not by increasing reactor operation frequency. An information and communication network system, therefore, is absolutely needed to support information exchange between the radioisotope producer, members of back up supply program and radioisotope customers

Guide-line of the radio-iodine (131I) therapy in Graves' disease and thyroid cancer

International Nuclear Information System (INIS)

Mori, Yutaka; Ikekubo, Katsuji

2005-01-01

Radio-iodine ( 131 I) therapy has been using in Graves' disease and well differentiated thyroid cancer. The rules of control in the discharge from radio-isotope hospital were notified in 1999 in Japan. Guideline of the 131 I therapy in Graves' disease and thyroid cancer were prepared by sub-group of Japanese Society of Nuclear Medicine. (author)

Radioisotopes production for applications on the health

International Nuclear Information System (INIS)

Monroy G, F.; Alanis M, J.

2010-01-01

In the Radioactive Materials Department of the Instituto Nacional de Investigaciones Nucleares (ININ) processes have been studied and developed for the radioisotopes production of interest in the medicine, research, industry and agriculture. In particular five new processes have been developed in the last 10 years by the group of the Radioactive Materials Research Laboratory to produce: 99 Mo/ 99m Tc and 188 W/ 188 Re generators, the radio lanthanides: 151 Pm, 147 Pm, 161 Tb, 166 Ho, 177 Lu, 131 I and the 32 P. All these radioisotopes are artificial and they can be produced in nuclear reactors and some of them in particle accelerators. The radioisotope generators are of particular interest, as those of 99 Mo/ 99m Tc and 188 W/ 188 Re presented in this work, because they are systems that allow to produce an artificial radioisotope of interest continually, in these cases the 99m Tc and the 188 Re, without the necessity of having a nuclear reactor or an particle accelerator. They are compact systems armored and sure perfectly of manipulating that, once the radioactive material has decayed, they do not present radiological risk some for the environment and the population. These systems are therefore of supreme utility in places where it is not had nuclear reactors or with a continuous radioisotope supply, due to their time of decaying, for its cost or for logistical problems in their supply, like it is the case of many hospital centers, of research or industries in our country. (Author)

Studies of /sup 131/I, /sup 137/Cs and /sup 103/Ru in milk, meat and vegetables in North East Scotland following the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Martin, C J; Heaton, B; Robb, J D

1988-01-01

Uptake and clearance of radionuclides in foodstuffs have been studied in the neighbourhood of Aberdeen in North East Scotland following the Chernobyl accident. The level of /sup 131/I in goats' milk was 100-200 Bq litre/sup -1/ in early May and declined with an effective half-life of 4.3 days, but that in cows's milk was only a few Bq litre/sup -1/ as most cattle were kept indoors. /sup 137/Cs and /sup 103/Ru activities in broccoli declined with effective half-lives of 11 and 6 days respectively, while /sup 137/Cs in grass decreased with a half-life of 22 days, the reduction appearing to show a relationship to weekly rainfall. Studies of tissues from groups of lambs initially grazed on contaminated pasture and later (a) fed indoors on concentrates or (b) continuing to graze outdoors, showed the /sup 137/Cs concentrations to decline with half-lives of (a) 17 days and (b) 25 days, while the half-lives describing the reduction in total /sup 137/Cs activity were (a) 20 days and (b) 35 days.

Manual on therapeutic uses of iodine-131. Incorporating: Applications guide, procedures guide, basics guide

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to therapeutic uses of Iodine-131: its application and procedures guides.

Manual on therapeutic uses of iodine-131. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

This publication is part of practical radiation safety manual series for different fields of application aimed primarily at persons handling radiation sources on a daily routine basis, which could at same time be used by the competent authorities, supporting their efforts in the radiation protection training of workers or medical assistance personnel or helping on-site management to set up local radiation protection rules. It is dedicated to therapeutic uses of Iodine-131: its application and procedures guides

Radioisotopes for nuclear medicine: the future

International Nuclear Information System (INIS)

Carr, S.W.

1998-01-01

Full text: Nuclear medicine occupies an important niche in the spectrum of medical capability. Since its initial application on a routine basis over 30 years ago its importance has continued to grow. For example, it is expected that over 430,000 Australians will have a nuclear medicine procedure in 1998. Current procedures using nuclear medicine are mainly concerned with diagnosis of oncology, cardiology and neurology. The main radioisotope used in nuclear medicine is Tc 99m, which is produced by a 'so called' Mo-Tc 99m generator. Other isotopes which currently find routine use are Ga-67, Th-201 and I-131. The selective uptakes by particular organs or structures is facilitated by the use of 'cold kits' which after the chemistry of the radioisotope many of the recent advances have been concerned with increasing the selectivity for a particular organ structure. Several of these new agents show increased selectivity using antibody a peptide recognition units

Predictive value of tracer studies for 131I treatment in hyperthyroid cats

International Nuclear Information System (INIS)

Broome, M.R.; Turrel, J.M.; Hays, M.T.

1988-01-01

In 76 cats with hyperthyroidism, peak thyroidal radioiodine ( 131 I) uptakes and effective half-lives were determined after administration of tracer and therapeutic activities of 131 I. In 6 additional hyperthyroid cats, only peak thyroidal uptakes after administration of tracer and therapeutic activities of 131 I were determined. Good correlation was found between peak thyroidal uptakes of tracer and therapeutic 131 I; however, only fair correlation was observed between effective half-lives. In 79% of the cats, the effective half-life for therapeutic 131 I was longer than that for tracer 131 I. After administration of therapeutic activity of 131 I, monoexponential and biphasic decay curves were observed in 51 and 16 cats, respectively. Using therapeutic kinetic data, radiation doses to the thyroid gland were calculated retrospectively on the basis of 2 methods for determining the activity of 131 I administered: (1) actual administration of tracer-compensated activity and (2) hypothetic administration of uniform activity (3 mCi). Because of the good predictive ability of tracer kinetic data for the therapeutic kinetic data, the tracer-compensated radiation doses came significantly (P = 0.008) closer to the therapeutic goal than did the uniform-activity doses. In addition, the use of tracer kinetic information reduced the extent of the tendency for consistently high uniform-activity doses. A manual method for acquiring tracer kinetic data was developed and was an acceptable alternative to computerized techniques. Adoption of this method gives individuals and institutions with limited finances the opportunity to characterize the iodine kinetics in cats before proceeding with administration of therapeutic activities of 131 I

Radioisotope Production for Medical and Physics Applications

Science.gov (United States)

Mausner, Leonard

2012-10-01

Radioisotopes are critical to the science and technology base of the US. Discoveries and applications made as a result of the availability of radioisotopes span widely from medicine, biology, physics, chemistry and homeland security. The clinical use of radioisotopes for medical diagnosis is the largest sector of use, with about 16 million procedures a year in the US. The use of ^99Mo/^99mTc generator and ^18F make up the majority, but ^201Tl, ^123I, ^111In, and ^67Ga are also used routinely to perform imaging of organ function. Application of radioisotopes for therapy is dominated by use of ^131I for thyroid malignancies, ^90Y for some solid tumors, and ^89Sr for bone cancer, but production of several more exotic species such as ^225Ac and ^211At are of significant current research interest. In physics ^225Ra is of interest for CP violation studies, and the actinides ^242Am, ^249Bk, and ^254Es are needed as targets for experiments to create superheavy elements. Large amounts of ^252Cf are needed as a fission source for the CARIBU experiment at ANL. The process of radioisotope production is multidisciplinary. Nuclear physics input based on nuclear reaction excitation function data is needed to choose an optimum target/projectile in order to maximize desired isotope production and minimize unwanted byproducts. Mechanical engineering is needed to address issues of target heating, induced mechanical stress and material compatibility of target and claddings. Radiochemists are involved as well since chemical separation to purify the desired final radioisotope product from the bulk target and impurities is also usually necessary. Most neutron rich species are produced at a few government and university reactors. Other radioisotopes are produced in cyclotrons in the commercial sector, university/hospital based facilities, and larger devices at the DOE labs. The landscape of US facilities, the techniques involved, and current supply challenges will be reviewed.

Renal excretion of iodine-131 labelled meta-iodobenzylguanidine and metabolites after therapeutic doses in patients suffering from different neural crest-derived tumours

International Nuclear Information System (INIS)

Wafelman, A.R.; Hoefnagel, C.A.; Maessen, H.J.M.; Maes, R.A.A.; Beijnen, J.H.

1997-01-01

Iodine-131 labelled meta-iodobenzylguanidine ([ 131 I[MIBG) is used for diagnostic scintigraphy and radionuclide therapy of neural crest-derived tumours. After administration of therapeutic doses of [ 131 I[MIBG (3.1-7.5 GBq) to 17 patients (n=32 courses), aged 2-73 years, 56%±10%, 73%±11%, 80%±10% and 83%±10% of the dose was cumulatively excreted as total radioactivity in urine at t=24 h, 48 h, 72 h and 96 h, respectively. Except for two adult patients, who showed excretion of 14%-18% of [ 131 I[meta-iodohippuric acid ([ 131 I[MIHA), the cumulatively excreted radioactivity consisted of >85% [ 131 I[MIBG, with 6% of the dose excreted as free [ 131 I[iodide, 4% as [ 131 I[MIHA and 2.5% as an unknown iodine-131 labelled metabolite. Cumulative renal excretion rates of total radioactivity and of [ 131 I[MIBG appeared to be higher in neuroblastoma and phaeochromocytoma patients than in carcinoid patients. Based on the excretion of small amounts of [ 131 I[meta-iodobenzoic acid in two patients, a possible metabolic pathway for [ 131 I[MIBG is suggested. The degree of metabolism was not related to the extent of liver uptake of radioactivity. (orig.). With 2 figs., 5 tabs

Comparison of conventional renal clearance values with differently evaluated results of radioisotope nephrography

International Nuclear Information System (INIS)

Grebe, S.F.; Weise, M.; Berghaeuser, H.; Faengewisch, G.L.; Temme, H.

1981-01-01

81 patients with renal anormalities or renal disorders of different genesis and severity with and without restricted renal functions were investigated by means of the classical PAH- and inulin-clearance. Furthermore a radioisotope nephrography was carried out after application of I 131-Hippuran followed by Cr 51-EDTA. In addition the activity reduction was measured above the shoulder, as well as the activity in serum samples and urine samples gained 30 min after application. A comparison of the clearance values found with those of conventional clearance resulted in poor correlation for I 131-Hippuran (r = 0.54) and no correlation for Cr 51-EDTA. Of the many parameters of the radioisotope nephrogram curves only the following are able to give sufficient quantitative functional results: The parameters connected with the rise of the curve between the 48sup(rh) and 120sup(rh) s and those connected with the slope of the secant. This is also true for the value of activity measured in the urine. (orig.) [de

Radioiodine 131 therapy in hyperthyroidism evaluation of French nuclear medicine practices

International Nuclear Information System (INIS)

Bernard, D.; Boin, C.; Desruet, M.; Roux, J.; Wolf, M.; Fagret, D.; Allenet, B.; Foroni, L.

2015-01-01

Full text of publication follows. Aim Radioiodine 131 I (RAI) is currently used routinely in the treatment of hyperthyroidism including Graves disease (GD), toxic multi-nodular goitre (TMNG) and toxic solitary nodule (TSN). It has proved to be safe, efficient and relatively inexpensive therapy. But after more than 60 years, many protocols are coexisting and no consensus exists on the most appropriate way to prescribe RAI dose: fixed dose regime or calculated doses based on gland size or turnover of RAI. This is the first nationwide French survey assessing the current practices about radioiodine treatment in thyrotoxicosis. Methods: we sent a questionnaire to French nuclear medicine hospital units and cancer treatment centres (n=69) about their practices in 2012. Questions were asked about RAI treatment: objectives, way to prescribe the therapeutic dose and its factors, radioisotope use to explore thyroid function and method of gland size measurement. Results: we received 40 responses. Euthyroidism was a successful treatment outcome for 33% of French respondents whereas hypothyroidism was the aim for 26%. Antithyroid drugs were stopped 7 days on average (range 3-21 days) before therapy. 68% of physicians used ultrasound for thyroid volume measurement. Calculated doses were used by 40% of clinicians (Marinelli's formula: 80%). Factors influencing prescription were thyroid uptake (100%) based on radiotracer iodine-131 (33%) or iodine-123 (67%), thyroid volume (93%) and disease (80%). Fixed activities represented 60% of the prescribed doses (72,5% for TMNG and TSN). The administered dose was chosen between 1 to 3 levels of standard doses, according to the patient characteristics. Factors influencing this choice were disease, with respectively a median of 370 MBq (range:185-740), 555 MBq (185-740), 555 MBq (296-925) for GD, TSN and TMNG, thyroid volume (59%) and thyroid uptake (52%) with the radiotracer iodine-123 (30%) or technetium-99m (70%). Even physicians

Studies on the production and application of radioisotopes

Energy Technology Data Exchange (ETDEWEB)

Han, Hyon Soo; Park, K. B.; Kim, J. R.; Yoon, B. M.; Bang, H. S.; Shin, B. C.; Cho, W. K.; Park, U. J.; Park, C. D.; Lee, Y. G.; Suh, C. H.; Shin, H. Y.; Kim, D. S.; Hong, S. B.; Jun, S. S.; Min, E. S.; Jang, K. D.; Kim, J. K.; Kim, S. J.; Yang, S. Y.; Yang, S. H.; Chun, K. J.; Kang, H. Y.; Suh, K. S.; Goo, J. H.; Chung, S. H.; Lee, J. C.; Choi, J. L.; Lee, H. Y.; Bang, K. S.

1997-09-01

To produce radioisotopes utilizing the research reactor `HANARO`, development of RI production process, target fabrication, preparation of devices and tools for RI process, preparation of production facility for radiopharmaceuticals, test production for the established process, etc. have been carried out, respectively. Production processes for various kinds of radionuclides were developed and the settled methods were applied to test production using `HANARO`. The results of developed process are as follows: (1) I-131 dry distillation method. (2) Large scale production of Ir-192 sources (3) P-32 production process by distillation under reduced pressure (4) Cr-51 production process using enriched target. To irradiate the target for RI production in `HANARO`, target for neutron irradiation, loading/unloading devices, working table in service pool, remote handling tools, shield cask for irradiated target transfer, etc. were designed and fabricated. The function test of prepared targets and the safety analysis of shielding casks were carried out. License for practical use of the prepared casks were obtained from Ministry of Science and Technology. For production of medical radioisotopes, their production facilities were designed in detail and were installed in RIPF (Radioisotope Production Facility), with full reflection of the basic concept of the good manufacturing practice for radiopharmaceuticals. The constructed GMP facilities have started to be operated after authorization since Jun., 1997. Results of this study will be applied to mass production of radioisotopes in `HANARO` and are to contribute the advance of domestic medicine and industry related to radioisotopes. (author). 7 refs., 7 tabs., 4 figs.

Studies on the production and application of radioisotopes

International Nuclear Information System (INIS)

Han, Hyon Soo; Park, K. B.; Kim, J. R.; Yoon, B. M.; Bang, H. S.; Shin, B. C.; Cho, W. K.; Park, U. J.; Park, C. D.; Lee, Y. G.; Suh, C. H.; Shin, H. Y.; Kim, D. S.; Hong, S. B.; Jun, S. S.; Min, E. S.; Jang, K. D.; Kim, J. K.; Kim, S. J.; Yang, S. Y.; Yang, S. H.; Chun, K. J.; Kang, H. Y.; Suh, K. S.; Goo, J. H.; Chung, S. H.; Lee, J. C.; Choi, J. L.; Lee, H. Y.; Bang, K. S.

1997-09-01

To produce radioisotopes utilizing the research reactor 'HANARO', development of RI production process, target fabrication, preparation of devices and tools for RI process, preparation of production facility for radiopharmaceuticals, test production for the established process, etc. have been carried out, respectively. Production processes for various kinds of radionuclides were developed and the settled methods were applied to test production using 'HANARO'. The results of developed process are as follows: 1) I-131 dry distillation method. 2) Large scale production of Ir-192 sources 3) P-32 production process by distillation under reduced pressure 4) Cr-51 production process using enriched target. To irradiate the target for RI production in 'HANARO', target for neutron irradiation, loading/unloading devices, working table in service pool, remote handling tools, shield cask for irradiated target transfer, etc. were designed and fabricated. The function test of prepared targets and the safety analysis of shielding casks were carried out. License for practical use of the prepared casks were obtained from Ministry of Science and Technology. For production of medical radioisotopes, their production facilities were designed in detail and were installed in RIPF (Radioisotope Production Facility), with full reflection of the basic concept of the good manufacturing practice for radiopharmaceuticals. The constructed GMP facilities have started to be operated after authorization since Jun., 1997. Results of this study will be applied to mass production of radioisotopes in 'HANARO' and are to contribute the advance of domestic medicine and industry related to radioisotopes. (author). 7 refs., 7 tabs., 4 figs

The 90Sr, 137Cs, 3H and 131I content in surface water and sediments of the Danube, Olt and Arges river and in milk samples for the year 1972

International Nuclear Information System (INIS)

Podeanu, G.; Iancu, E.

1975-01-01

The radioactivity of the measured radionuclides in water decreased from their discharge into the Danube to the mouth of the river. The amounts of certain radioisotopes in water samples, sediments, and milk are far below the maximum permissible concentrations. With some exceptions, the radioactivity of 137 Cs is lower than that of 90 Sr. With some exceptions, the highest values for the radionuclides studied were measured during the summer months. (orig./RW) [de

Evaluation of radiophoby phenomenon among patients undergoing radioisotope therapy

International Nuclear Information System (INIS)

Stepien, M.; Stepien, A.; Pawlus, J.; Wasilewska-Radwanska, M.

2005-01-01

The aim of study was to evaluate the radiophoby symptoms among 81 patients with different type hyperthyroidism undergoing 1-131 (450-600 MBq) treatment. The state anxiety as well as the trait anxiety levels using Spielberger's scale have been evaluated. Its values were 1 - 6 points (average 3) and 3 - 7 points (average 6) respectively for state anxiety and trait one. These results indicated that radioisotope therapy causes increase of patient's anxiety level. (author)

Application state of radioisotopes for medical use

International Nuclear Information System (INIS)

Nakajima, Tomoyoshi

1979-01-01

Application of unsealed radioisotopes as radiopharmaceuticals has been increasing year by year with the development of nuclear medicine. As for the radioisotopes for in vivo use which are internally administered and are detected by external scanning, the consumption of Tc-99 m drugs has increased rapidly. The sales of radiopharmaceuticals for in vivo use including 131 I, etc. amounted to four billion Yen in 1977. The consumption of the isotopes used in vitro for radioimmunoassay has made more rapid increase, and the sales of radiopharmaceuticals for in vitro use amounted to seven billion Yen in 1977. Radiopharmaceuticals have been used in 1,134 institutes all over Japan in 1978. 534 among them have applied radiopharmaceuticals to both in vivo and in vitro uses. Radioactive wastes have been increasing with the application of these unsealed radiopharmaceuticals, and their disposal method should be examined as there is a limit in their storage. (Kobatake, H.)

Sorption and desorption of Sr-90 and Cs-137 by sediments of the Sozh-river valley and border water collections

International Nuclear Information System (INIS)

Onoshko, M.P.

2001-01-01

From the last literature analysis it follows, that to studying of sorption and desorption soil, some rocks and minerals properties concerning radioisotopes the steadfast attention of researchers is paid nowadays. The materials of heavy particles sorption kinetics, the action of adsorption molecules and ions from solutions on leaching products are examined. Sr-90, Cs-137, Pu-239,240 diffusion is estimated. It is found out, that sorbed and desorbed amount of radioisotopes is proportionally to their concentration in soil, and sorption (S) and distributions (Cd) factors do not depend on soil contamination density, and are determined by its physical and chemical properties, parity of firm and liquid phases. It is judged, that increase of soil absorbing properties by the increase of sorbent entering are unpromising, as sorption soil capacity is filled by Cs-137 only in thousand shares of per cent from the sorbent amount, which can be absorbed by soil. With the reference to the conditions of Belarus, experiments and natural supervision on Sr-90 and Cs-137 sorption by Fe, Mn, Si, Al, Ti hydroxides were executed. At experimental researches of electrolyte influence on radioisotope sorption by peat soils Cd amount lines were established. Sediments under certain conditions, due to desorption, become a source of the secondary contamination of natural waters up to ecologically dangerous concentration. Radioisotopes desorption ambiguity is connected to many parallel proceeding processes: exchange sorption on organic and mineral components, co-sedimentation with one-and-a-half Fe, Al and Mn hydroxides and also depends on solutions structure, cationic exchange rocks and soil capacities, concentration of competing ions. At low radioisotopes contents desorption is insignificant, at high - their extraction does not depend on reagent concentration. We carried out the experiment on studying Cs-137 and Sr-90 sorption-desorption from sediments Sozh-river valley and border water

Geochronology of Lake Baikal from 210Pb and 137Cs radioisotopes

International Nuclear Information System (INIS)

Carroll, J.; Williamson, M.; Lerche, I.; Karabanov, E.; Williams, D.F.

1999-01-01

Two box cores of near surface sediments were obtained from Lake Baikal in Southeastern Siberia, Russia. The cores were taken from the northern and southern basins of the lake during a joint American-Russian research expedition in the summer of 1994. The cores were analyzed for 210 Pb, 137 Cs and total organic carbon (TOC). Organic carbon is an indicator of photosynthetic production by phytoplankton, taking place primarily in the euphotic zone of the water column. Accumulation rates of TOC may be used as indicators of paleo-productivity when sedimentation rates are determined using the 210 Pb dating method and combined with both the density of sediment and organic carbon content. Accordingly, the lake is characterized by changes in accumulations of TOC, which may be linked to rates of sedimentation. Accumulations of TOC and sedimentation rates were higher in the southern basin site than in the northern basin site. The southern station core was taken from an area in close proximity to the Selenga River delta, which carries 50% of the water input to Lake Baikal. Productivity should thus be higher in this region due to the high nutrient input and sediment accumulation higher due to influx of riverine sediment input. Traces of 137 Cs (an anthropogenic product) were found in both cores. However, activities of 137 Cs were significantly higher in the southern basin, likely due to the input of the Selenga River in the southern region, which extends to a region in Mongolia in close proximity to the area of the Chinese atomic-bomb atmospheric testing of the 1970s. Application of a quantitative inverse model to the 210 Pb profiles yielded the following results: (i) station 12, near the Selenga Delta, had an accumulation rate of about 0.38 cm/y in 1957 but this rate was halved by 1980 to about 0.22 cm/y and has been roughly steady since that time; 137 Cs values are consistent with the age-to-depth determination from 210 Pb for station 12; (ii) since about 1960, station 5A in

Critical assessment of radioisotopic methods used in the evaluation of pherispheral blood flow

International Nuclear Information System (INIS)

Kauffman, P.; Camargo, E.E.; Wolosker, M.; Dias Neto, A.L.; Carvalho, N.; Leao, L.E.P.

1974-01-01

A critical analysis of the radioisotope methods for studying peripheral blood flow is made. Methods using muscle injection of tracer and other ones using both the venous and the arterial routes of injection are discussed. Emphasys in the use of hippuran- 131 I for evaluating of the peripheral circulation dynamics is given [pt

Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Duong Van Dong; Pham Ngoc Dien; Bui Van Cuong; Mai Phuoc Tho; Nguyen Thi Thu; Vo Thi Cam Hoa

2014-01-01

After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated on March 20th, 1984 with the nominal power of 500 kW. Since then the production of radioisotopes and labelled compounds for medical use was started. Up to now, DNRR is still the unique one in Vietnam. The reactor has been operated safely and effectively with the total of about 37,800 hrs (approximately 1,300 hours per year). More than 90% of its operation time and over 80% of its irradiation capacity have been exploited for research and production of radioisotopes. This paper gives an outline of the radioisotope production programme using the DNRR. The production laboratory and facilities including the nuclear reactor with its irradiation positions and characteristics, hot cells, production lines and equipment for the production of Kits for labelling with 99m Tc and for quality control, as well as the production rate are mentioned. The methods used for production of 131 I, 99m Tc, 51 Cr, 32 P, etc. and the procedures for preparation of radiopharmaceuticals are described briefly. Status of utilization of domestic radioisotopes and radiopharmaceuticals in Vietnam is also reported. (author)

Observation of high spin levels in Cs from Ba decay

Indian Academy of Sciences (India)

physics pp. 1157–1162. Observation of high spin levels in. 131. Cs from. 131. Ba decay. M SAINATH, DWARAKA RANI RAO*, K VENKATARAMANIAH and P C SOOD. Department of Physics, Sri Sathya Sai Institute of Higher Learning, Prasanthinilayam 515 134, India. £Permanent address: Department of Physics, ...

Radioisotopes for therapy: an overview

International Nuclear Information System (INIS)

Venkatesh, Meera

2006-01-01

Radionuclides made great impact in the history of nuclear sciences both at the end of 19th century with the discoveries of Becquerel and madame Curie and later in 1934, when Frederic Joliet and Irene Curie demonstrated the production of the first artificial radioisotopes, 30 P, by bombardment of 27 Al by alpha particles. The subsequent invention of cyclotron and setting up of nuclear reactor opened the floodgate for production of artificial radionuclides. Currently, majority of radionuclides are made artificially by transforming a stable nuclide into an unstable state and thus far over 2500 radionuclides have been produced artificially. Use of radionuclides in various fields immediately followed their production and last century has witnessed tremendous growth in the applications of radiation and radioisotopes, in diverse fields such as medicine, industry, agriculture, food preservation, water resource management, environmental studies, etc. While radiation and radioisotopes are used both for diagnosis as well as for therapy in the field of medicine, therapeutic applications are among the earliest, which began as an empirical science in the beginning and developed into a well structured modality with time. (author)

Determination of {sup 131}I and thorium in urine; Determinacao de iodo-131 e torio em urina

Energy Technology Data Exchange (ETDEWEB)

Tomida, Rute Miwa

1978-07-01

Methods for the determination of {sup 131}I and Thorium in urine have been developed taking into account the monitoring needs for people who handle with these radioisotopes. The method for determining {sup 131}I is based in the use of silver chloride to separate iodine by precipitation from the sample; the detection was carried out in a Nal (Tl) well type scintillator connected to a single channel analyser. This method has the following advantages; it is easy and relatively fast as well as selective, showing a separation yield higher than 80%. Thorium in urine was determined by colorimetry after the mineralization of the sample using nitric acid, and sulphuric acid, and then oxygen peroxide. The chromophore reagent used was Thoron (disodium salt of 2-(2-hydroxy-3,6-disulfo-l-naphthylazo) benzenearsonic acid).The absorbance was measured in a spectro colorimeter at a fixed wavelength (530 nm). The method proved to be simple allowing a separation yield of about 80%. The most representative sample for a monitoring program in a {sup 131}I production laboratory has been established. The {sup 131}I concentration in urine of individuals with chronic contamination have also been measured; an interpretation of these results is discussed. (author)

Radiation risk assessment for the transport of radioisotopes using KRI-BGM B(U) type container

International Nuclear Information System (INIS)

Cho, Woon-Kap

2008-01-01

The radiation risks were estimated for the transportation of radioisotopes using KRI-BGM transport container. KRI-BGM container was specially designed for transportation of large amount of radioisotopes for industrial or medical applications. The container can carry maximum 370 TBq of solid Ir-192, 29.6 TBq of liquid Mo-99 and 37 TBq of liquid I-131 respectively. For the radiation risk assessment, it was assumed that maximum design activity of those radioisotopes was transported. Transportation route is from Daejeon where radioisotopes are produced to Seoul where radioisotopes are consumed. Transport distance is 200 km including highway and downtown area from Daejeon to Seoul. As the transportation conveyance, an ordinary cargo truck is used exclusively. Radiation risks were estimated for incident free and accident condition of transportation and RADTRAN 5.6 was used as the risk assessment tool. For the risk assessment of radioisotopes transportation, various parameters such as population density around transport route, weather condition, probability of specific accidents such as impact, fire, etc. were considered. From the results of this study, the exclusive transportation of radioisotopes using KRI-BGM transport container by truck showed low radiological risks with manageable safety and health consequences. This paper discusses the methods and results of the radiation risks assessment for the radioisotopes transportation by an ordinary truck and presents the expected radiation risks in person-Sv and latent cancer fatalities. (author)

Radioisotopic studies in renal transplantation

International Nuclear Information System (INIS)

Levasseur, A.; Robillard, R.; Lemieux, R.; Dandavino, R.; Girard, R.

1981-01-01

Radioisotopic evaluation of kidney graft function has greatly reduced the need for more invasive studies such as arteriography, retrograde pyelograpy and graft biopsy. The schedule of sequential studies beginning the day after transplant may be modified according to the patient's clinical or biochemical status. The combined use of I 131 Hippuran and sup(99m)Tc DTPA allows early detection of graft rejection and its differentiation from tubular necrosis. Scintigraphic images may have a characteristic appearance in cases of arterial, venous or urinary obstruction, urinary fistule, infarction, abcess and lymphocele. This non-invasive diagnostic study requiring only an intravenous injection is simple, rapid, accurate and may be repeated as often as necessary. (auth) [fr

Studies of radioactivity of vegetables: determination of transfer factors 85Sr and 134Cs in some vegetables

International Nuclear Information System (INIS)

Oncsik, M.B.

1999-01-01

The radioisotope uptake of potato and culinary dry bean was studied in field experiments on meadow soil enriched with vermiculite and humanite by artificial soil contamination. The isotope uptake from the soil was characterized by a transfer factor (TF). Based on the results of the potato experiment it was found that the TF value characterizing the 134 Cs contamination of the crop, changed between 1.31 - 0.77*10 -4 m 2 (kg dry matter) -1 on high humus content soil (treated with humanite) and on soil treated with vermiculite, while it was 22-45 % higher in plants grown on the radioactive control plots. lt was 1.69*10 -4 m 2 (kg dry matter)2 -1 in average. The TF values of 85 Sr uptake of potato are several times higher than those of experiments treated by isotope 134 Cs. The TF values fluctuated between 5.30-7.33*10 -4 m 2 (kg dry matter) -1 in soils treated with the additives, while on the plots with radioactive contamination it was 8.42*10 -4 m 2 (kg dry matter) -1 . Based on the results of 134 Cs studies of edible part of dry bean, it could be stated that after the soil contamination the TF value was 0.99*10 -4 m 2 (kg dry matter) -1 in average. According to the activity results of the experiments there was significant difference between the contamination of the plant parts. Refs. 6 (author)

Multiple model testing using Chernobyl fallout data of I-131 in forage and milk and Cs-137 in forage, milk, beef and grain. Pt. 2

International Nuclear Information System (INIS)

1991-03-01

BIOMOVS is an international study for testing and validating model predictions of the transfer of radionuclides and rare stable elements through the biosphere. The BIOMOVS A4 scenario was designed to test model prediction of the transfer of I-131 and Cs-137 from the atmosphere via pasture vegetation to milk and of the Cs-137 transfer from air to beef (via vegetation) and grain. This document is an appendix to the A4 report. It includes tables and figures of time-integrated results, a summary of a statistical analysis of time-dependent and representative figures of time-dependent results. The quantities to be predicted in this scenario were wet, dry and total deposition (Bq m -2 ) of I-131 and Cs-137, contamination of vegetation (Bq kg -1 d.w.), milk (Bq L -1 ), beef and grain (Bq kg -1 ). While with steady state models only time-integrated results for vegetation, milk and beef could be calculated, these quantities also were requested as time-series from users of dynamic models. A detailed description of the participating models is given in Appendix 3, while all collected observations are documented in Appendix 2 of the A4 report. A diskette with all observed data can be obtained from the Swedish National Institute of Radiation Protection, SSI, or from Harry Koehler, IAEA, Vienna, Austria. For time-integrated P/Os, graphs for all locations and all models and sometimes subsets of these are provided. For time-series, graphs are enclosed for the observations and some model results. These values are calculated across locations and across models for time-integrated predictions and for the P/O of entire time-series and subsets of these for the time-dependent predictions. (au)

123I and 13I purification for biomolecules labelling

International Nuclear Information System (INIS)

Catanoso, Marcela Forli

2011-01-01

The 123 I and 131 I are iodine radioisotopes widely used in Nuclear Medicine. The radioisotope 123 I is used in diagnosis through the SPECT technique and is routinely produced at IPEN in cyclotron through the reaction: '1 24 Xe (p, 2n) '1 23 Cs -> 123 Xe -> 123 I. The radioisotope 131 I is used both in diagnosis and therapy due to its physical characteristics of decay by β - and its γ-ray emissions that are softened with the use of specific collimators for diagnosis. It is routinely produced at IPEN using the nuclear reactor through the indirect reaction: 130 Te (n, γ) -> 131 Te -> 131 I, irradiating compounds containing Te. The radiopharmaceuticals prepared with these radioisotopes go through rigorous quality control tests and the chemical purity of the primary radioisotopes 123 I and 131 I are within the permissible limits currently defined. However, the presence of some chemical contaminants can prejudice the biomolecules labeling (monoclonal antibodies and peptides), that will produce radiopharmaceuticals of first generation to the oncology area. The aim of this work was to obtain a new purification method of these radioisotopes, allowing the labeling of biomolecules and also to established a process control on those radioisotopes. The methodology was separated on 3 steps: Evaluation of '1 23 I e 131 I radionuclidic purity using a hyper pure germanium detector, chemical purity using ICP-OES and the retention and elution study of 131 I in several absorbers to choose the most appropriate for the purification tests analyzing the behavior of the possible contaminants. The radionuclidic analyses showed the presence of Te and Co on 131 I samples and Te, Tc e Co on 123 I samples. The chemical purity analyses showed the presence of Al and Mo in 123 I, coming from the window material of the target holder and the presence of Al and Te in 131 I samples, coming from the target holder and the target, respectively. The retention and elution study selected the most

The Current Utilization and Future Demand of Radiopharmaceutical and Radioisotopes in Malaysia

International Nuclear Information System (INIS)

Ibrahim Ijang; Zakaria Ibrahim; Bohari Yaacob

2013-01-01

Radioisotope and pharmaceutical kits play an important role in nuclear medicine for non-invasive diagnosis and treatment of various cancers and cardiovascular disease. Our aim was to survey the current utilization and future demand of radiopharmaceuticals and radioisotopes in Malaysia. The survey methodology technique was done using questionnaire administration modes. The survey was done for four month duration from government hospitals that have nuclear medicine department. The most frequent pharmaceutical kits used in hospitals were Methylene Diphosphonic acid (MDP) for bone imaging and Diethylene Triamine Pantacetic acid (DTPA). Similarly radioisotopes widely used were Tc-99m and Iodine 131.Therefore if produced of Tc-99m by Nuclear Malaysia can improved in term of high quality products, Nuclear Malaysia could be the sole supplier of this product to hospitals in Malaysia. Similarly pharmaceutical kits especially MDP and DTPA, Nuclear Malaysia has the expertise and knowledge to supply these kits to the hospital. (author)

Vertical migration of 85Sr, 137Cs and 131I in various arable and undisturbed soils

International Nuclear Information System (INIS)

Palagyi, S.; Palagyiova, J.

2002-01-01

Vertical migration of 85 Sr, 137 Cs and 131 I in some arable and undisturbed single-contaminated soils was studied by gamma-spectrometry measurements in lysimetric laboratory conditions applying irrigation of the soil profiles with wet atmospheric precipitation for about one year (except radioiodine). A new simple exponential compartment (box) model was derived, allowing us to calculate the migration rate constants and migration rates in the individual soil layers (vertical sections) as well as the total vertical migration rate constants and total vertical migration rates of radionuclides in the bulk soil horizon. The data from the time dependence of the depth activity distribution (radionuclide concentration along the vertical soil profile) were used to test the model. The migration rate constants and migration rates were found to be affected by the contaminating radionuclides as well as by the site, type and depth of the soil. The relaxation times of the radionuclides in the soil horizons were calculated. The effects on the rate parameters of the permanent grass cover and the zeolite applied onto the arable soil surfaces were also investigated

Radioisotope production in Malaysia

Energy Technology Data Exchange (ETDEWEB)

Wan Awang, Wan Anuar [Medical Technology Div., Malaysian Inst. for Nuclear Technology Research (MINT) (Malaysia)

1998-10-01

Production of Mo-99 by neutron activation of Mo-99 in Malaysia began as early as 1984. Regular supply of the Tc-99m extracted from it to the hospitals began in early 1988 after going through formal registration with the Malaysian Ministry of Health. Initially, the weekly demand was about 1.2 Ci of Mo-99 which catered the needs of 3 nuclear medicine centres. Sensitive to the increasing demand of Tc-99m, we have producing our own Tc-99m generator from imported TeO{sub 2} because irradiation TeO{sub 2} with our reactor give low yield of I-131. We have established the production of radioisotope for industrial use. By next year, Sm-153 EDTMP will be produce after we have license from our competent authority. (author)

Radioisotope instruments

CERN Document Server

Cameron, J F; Silverleaf, D J

1971-01-01

International Series of Monographs in Nuclear Energy, Volume 107: Radioisotope Instruments, Part 1 focuses on the design and applications of instruments based on the radiation released by radioactive substances. The book first offers information on the physical basis of radioisotope instruments; technical and economic advantages of radioisotope instruments; and radiation hazard. The manuscript then discusses commercial radioisotope instruments, including radiation sources and detectors, computing and control units, and measuring heads. The text describes the applications of radioisotop

Radioisotope programme in India: past, present and future

International Nuclear Information System (INIS)

Kohli, A.K.

2012-01-01

One of the major discoveries of the 20th century is the discovery of artificial radioactivity. This distinctive discovery in human history transformed atoms of one element to another. Until then, chemical reactions used to be concerned only with changes occurring outside the nucleus. The field of nuclear science came into existence with discovery of X-rays by Wilhelm Roentgen in 1895, radioactivity emitted by Uranium salt by Henri Becquerel in 1896 and pioneering work carried out by Madame Curie and Pierre Curie. India's atomic energy programme was envisaged, founded and developed by the great visionary Dr. Homi Jehangir Bhabha. Since then Department of Atomic Energy (DAE) of Government of India has been engaged in developing technologies for use of radiation in all possible fields for the benefit of society. The most common sources of radiation are radioisotopes. Radioisotopes are produced by nuclear reactors either by utilizing available excess neutrons for activation of stable elements or by separating useful fission products from the spent fuel. In India, the production of radioisotopes started with the commissioning of APSARA reactor in 1956. Initially, APSARA was operated at low power, and radioisotopes could be produced only on a small scale. All these operations had to be called out with remote handling or in the safe glove boxes keeping in view the radiation levels associated with the samples. In due course, the reactor reached full power and remotely operated processing equipment required for handling the radioisotopes were set up. Isotopes such as Iodine-131, Phosphorous-32, Gold-198 and Sodium-24 were produced and extracted in purified form in small quantities. These were given to KEM Hospital and Bombay Hospital at Mumbai, Vallabhbhai Patel Chest Institute and Safdarjung Hospital in Delhi, mainly for exploratory experiments

Radiochemical determination of 137Cs in foods

International Nuclear Information System (INIS)

Kastner, Geraldo F.; Ferreira, Andrea Vidal; Monteiro, Roberto P.G.

2013-01-01

A determination of radionuclides in food samples is important in commodities in order to attend to regulatory requirements for international trade. As a long-lived radioisotope of cesium, 137 Cs is produced as a result of human nuclear activities and than its contamination level evaluation among others radionuclides in foods is necessary. A methodology for the determination of 137 Cs in foods, pork and fish, is described. The procedures covered homogenization and freeze-drying of the samples. The 137 Cs was measured by gamma spectrometry using Canberra 50% HPGe detector. The counting was carried out with Monte Carlo software for detection conditions optimization including geometry and chemical data information. A certified sample, SRM IAEA-375, was analyzed in order to evaluate the reliability of the method, and the results showed good agreement between the measured and certified values. (author)

Comparison of thallium-201, Tc-99m MIBI and I-131 scan in the follow-up assessment after I-131 ablative therapy in differentiated thyroid cancer

International Nuclear Information System (INIS)

Kwon, Jae Sung; Lee, Sung Keun; Kim, Doe Min; Park, Sae Jong; Jang, Kyong Sun; Kim, Eun Sil; Kim, Chong Soon

1999-01-01

We conducted a comparative study to evaluate the diagnostic values of Tl-201, Tc-99m MIBI and I-131 scans in the follow-up assessment after ablative I-131 therapy in differentiated thyroid cancer. The study population consisted of 20 patients who underwent surgical removal of thyroid cancer and ablative radioactive iodine therapy, and followed by one or more times of I-131 retreatment (33 cases). In all patients, Tl-201, Tc-99m MIBI, diagnostic and therapeutic I-131 scans were performed and the results were analyzed retrospectively. Also serum thyroglobulin levels were measured in all patients. The final diagnosis of recurrent or metastatic thyroid cancer was determined by clinical, biochemical, radiologic and/or biopsy findings. Positive rates (PR) of Tc-99m MIBI, Tl-201, diagnostic and therapeutic I-131 scans in detecting malignant thyroid tissue lesions were 70% (19/27), 54% (15/28), 35% (17/48) and 63% (30/48), respectively. The PR in the group of 20 cases (28 lesions) who underwent concomitant Tl-201 and I-131 scans were in the order of therapeutic 131 scan 71%, Tl-201 scan 54% and diagnostic I-131 scan 36%. There was no statistically significant difference between Tl-201 and diagnostic I-131 scans (p>0.05). In the group of 20 cases (27 lesions) who underwent concomitant Tc-99m MIBI and I-131 scans, the PR were in the order of Tc-99m MIBI scan 70%, I-131 therapeutic scan 52% and I-131 diagnostic scan 33%. The PR of Tc-99m MIBI was significantly higher than that of diagnostic I-131 scan (p<0.05). Tc-99m MIBI scan is superior to diagnostic I-131 scan in detecting recurrent or metastatic thyroid cancer following ablation therapy in patients with differentiated thyroid cancer. Tl-201 scan did not showed significantly higher positive rate than diagnostic I-131 scan. Instead of diagnostic I-131 scan before the I-131 retreatment, Tc-99m MIBI scan without discontinuing thyroid hormone replacement would be a prudent and effective approach in the management of these

Determination of 131I and thorium in urine

International Nuclear Information System (INIS)

Tomida, Rute Miwa

1978-01-01

Methods for the determination of 131 I and Thorium in urine have been developed taking into account the monitoring needs for people who handle with these radioisotopes. The method for determining 131 I is based in the use of silver chloride to separate iodine by precipitation from the sample; the detection was carried out in a Nal (Tl) well type scintillator connected to a single channel analyser. This method has the following advantages; it is easy and relatively fast as well as selective, showing a separation yield higher than 80%. Thorium in urine was determined by colorimetry after the mineralization of the sample using nitric acid, and sulphuric acid, and then oxygen peroxide. The chromophore reagent used was Thoron (disodium salt of 2-(2-hydroxy-3,6-disulfo-l-naphthylazo) benzenearsonic acid).The absorbance was measured in a spectro colorimeter at a fixed wavelength (530 nm). The method proved to be simple allowing a separation yield of about 80%. The most representative sample for a monitoring program in a 131 I production laboratory has been established. The 131 I concentration in urine of individuals with chronic contamination have also been measured; an interpretation of these results is discussed. (author)

Present status and prospect of radiation and radioisotopes in China

International Nuclear Information System (INIS)

Zhou, Yong-Tian

1986-01-01

Production and application of radioisotopes in China started almost thirty years ago. At present there are 20 units producing more than 700 radioisotope products. This report outlines the present status and prospect of radiation and radioisotopes in some major areas. Remarkable achievements have been made in agriculture using nuclear technology. More than 70 new varieties or strains of cultivated plants have been bred by inducing mutation through irradiation. A new variety of silkworm bred by irradiation has unique characteristics such as high and stable yield. Application of radioisotopes in medical research and clinical practice began in 1956 and radionuclides have been progressively used in diagnosis and treatment of diseases. The most common radionuclide used in therapy is iodine-131 for hyperthyroidism. Isotope-tracer technique and activation analysis play an important role in the study of traditional Chinese medicine. Isotope methods in China have been used in many industrial branches, such as textile, plastic and printing, but not very widely now. The nation has produced more than 2,000 sets of nuclear radiation measuring instruments, which become important parts of industrial automation control. The radiation processing research started in the end of 1950's. Food irradiation research has been going on in a good cooperation of different branches. Now China is planning to set up some plants to produce gamma irradiated disposal syringes and other medical devices. (Nogami, K.)

Merkel cell carcinoma and iodine-131 metaiodobenzylguanidine scan

International Nuclear Information System (INIS)

Castagnoli, A.; Biti, G.; De Cristofaro, M.T.R.; Papi, M.G.; Ferri, P.; Magrini, S.M.; Bianchi, S.

1992-01-01

Two cases of Merkel cell carcinoma, a neuroendocrine neoplasia of the skin, investigated with iodine, 131 metaiodobenzylguanidine ( 131 I-mIBG) scintigraphy, are reported. Uptake in the tumor was evident only in 1 case. The possible diagnostic and therapeutic role of 131 I-mIBG in patients with this rare neoplasm is discussed. (orig.)

Dosimetric characterization of model Cs-1 Rev2 cesium-131 brachytherapy source in water phantoms and human tissues with MCNP5 Monte Carlo simulation

International Nuclear Information System (INIS)

Wang Jianhua; Zhang Hualin

2008-01-01

A recently developed alternative brachytherapy seed, Cs-1 Rev2 cesium-131, has begun to be used in clinical practice. The dosimetric characteristics of this source in various media, particularly in human tissues, have not been fully evaluated. The aim of this study was to calculate the dosimetric parameters for the Cs-1 Rev2 cesium-131 seed following the recommendations of the AAPM TG-43U1 report [Rivard et al., Med. Phys. 31, 633-674 (2004)] for new sources in brachytherapy applications. Dose rate constants, radial dose functions, and anisotropy functions of the source in water, Virtual Water, and relevant human soft tissues were calculated using MCNP5 Monte Carlo simulations following the TG-43U1 formalism. The results yielded dose rate constants of 1.048, 1.024, 1.041, and 1.044 cGy h -1 U -1 in water, Virtual Water, muscle, and prostate tissue, respectively. The conversion factor for this new source between water and Virtual Water was 1.02, between muscle and water was 1.006, and between prostate and water was 1.004. The authors' calculation of anisotropy functions in a Virtual Water phantom agreed closely with Murphy's measurements [Murphy et al., Med. Phys. 31, 1529-1538 (2004)]. Our calculations of the radial dose function in water and Virtual Water have good agreement with those in previous experimental and Monte Carlo studies. The TG-43U1 parameters for clinical applications in water, muscle, and prostate tissue are presented in this work

Effect of mycorrhizal infection on root uptake by pine seedlings and redistribution of three contrasting radio-isotopes: 85Sr, 95mTc and 137Cs

International Nuclear Information System (INIS)

Plassard, C.; Ladeyn, I.; Staunton, S.

2004-01-01

Mycorrhizal infection is known to improve phosphate nutrition and water supply of higher plants. It has been reported to both increase the uptake of potentially toxic pollutant elements and to protect plants against toxic effects. Little is known about the effect of mycorrhizal infection on the dynamics of radioactive pollutants in soil-plant systems. The aim of this study was to compare the root uptake and root-shoot transfer of three radio-isotopes with contrasting chemical properties ( 85 Sr, 95m Tc and 137 Cs) in mycorrhizal and control, non mycorrhizal plants. The plant studied was Pinus pinaster and the associated ecto-mycorrhizal fungus was Rhizopogon roseolus (strain R18-2). Plants were grown under anoxic conditions for 3 months then transferred to thin layers of autoclaved soil and allowed to grow for four months. After this period, the rhizotrons were dismantled, and plant tissue analysed. Biomass, nutrient content (K, P, N, Ca) and activities of each isotope in roots, shoots and stems were measured, and the degree of mycorrhizal infection assessed. The transfer factors decreased in the order Tc>Sr>Cs as expected from the degree of immobilisation by soil. No effect of mycorrhizal infection on root uptake was observed for Sr. Shoot activity concentration of Tc was decreased by mycorrhizal infection but root uptake correlated well with mycelial soil surface area. In contrast, Cs shoot activity was greater in mycorrhizal than control plants. The uptake and root to shoot distribution shall be discussed in relation to nutrient dynamics. (author)

Operation status and prospect of radioisotope production facility in HANARO

International Nuclear Information System (INIS)

Kim, Minjin; Jung, H.S.

2012-01-01

At the RIPF at HANARO, Radioisotopes for industrial and medical purpose are produced and research and development for various radioisotopes are carried out. Major products include Ir-192 for NDT, I-131 for treatment and diagnosis of thyroid cancer, Mo-99/Tc-99m Generator for imaging diagnosis of cancer. Production of radioisotope and radiopharmaceutical is being increased every year. Due to world-wide unstableness in the supply of Mo-99, a technology to produce (n,γ)Mo-99 generator at HANARO had been developed as a short term countermeasure. It will be available by the end of 2012. As a long term countermeasure, we are trying to build a new fully dedicated isotope reactor that will produce Fission Mo-99. At present, utilization of RIPF at HANARO is being increased. However when the construction of a new dedicated isotope reactor is completed in 2016, the role of the existing facility and new facility should be established accordingly so that none of the facilities are idling. In the near future, when the prospect of a utilization plan is completed, we expect an opportunity to present the result. (author)

Feasibility study for production of I-131 radioisotope using MNSR research reactor

Energy Technology Data Exchange (ETDEWEB)

Elom Achoribo, A.S., E-mail: achoribo@yahoo.fr [Radiological and Medical Sciences Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon Accra (Ghana); Akaho, Edward H.K. [Ghana Atomic Energy Commission, P.O. Box LG80, Legon Accra (Ghana); Nyarko, Benjamin J.B.; Osae Shiloh, K.D. [National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon Accra (Ghana); Odame Duodu, Godfred [Radiological and Medical Sciences Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon Accra (Ghana); Gibrilla, Abass [National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG80, Legon Accra (Ghana)

2012-01-15

A feasibility study for {sup 131}I production using a Low Power Research Reactor was conducted to predict the yield of {sup 131}I by cyclic activation technique. A maximum activity of 5.1 GBq was achieved through simulation using FORTRAN 90, for an irradiation of 6 h. But experimentally only 4 h irradiation could be done, which resulted in an activity of 4.0 Multiplication-Sign 10{sup 5} Bq. The discrepancy in the activities was due to the fact that beta decays released during the process could not be considered. - Highlights: Black-Right-Pointing-Pointer For a high irradiation time, the neutron flux will give high activity. Black-Right-Pointing-Pointer For maximum number of irradiation that can be done a maximum activity could be obtained. Black-Right-Pointing-Pointer An idea on how to maximize the activity (recommendation).

Linhchi mushrooms as biological monitors for 137Cs pollution

International Nuclear Information System (INIS)

Tran Van, L.; Le Duy, T.

1991-01-01

Radioactivity of Linhchi mushrooms (Ganoderma Lucidum) cultivated in laboratory and production conditions has been measured in the Environmental Laboratory of Nuclear Research Institute (NRI), Dalat, Vietnam. The results showed that Linhchi mushroom has a high radioactive concentration of 137 Cs, which is about 20 Bq kg -1 fresh weight. In addition, the radioactive contents of substrata before and after cultivation were insignificant. This suggested that Linhchi mushroom should only accumulate the 137 Cs radioisotope from the atmosphere, directly. Therefore, it should be considered as a bio-indicator for environmental monitoring. (author) 13 refs.; 3 figs.; 2 tabs

General dosimetry model for internal contamination with radioisotopes

International Nuclear Information System (INIS)

Nino, L.

1989-01-01

Radiation dose by inner contamination with radioisotopes is not measured directly but evaluated by the application of mathematical models of fixation and elimination, taken into account biological activity of each organ with respect to the incorporated material. Models proposed by ICRP for the respiratory and gastrointestinal tracts (30) seems that they should not be applied independently because of the evident correlation between them. In this paper both models are integrated in a more general one with neither modification nor limitation of the starting models. It has been applied to some patients in the Instituto Nacional de Cancerologia, who received some I-131 dose via oral and results are quite similar to dose experimentally obtained via urine spectrograms. Based on this results the method was formalized and applied to professional exposed personnel of the medical staff at the same Institute; due to high doses found in some of the urine samples, probable I-131 air contamination could be supposed

Radioisotope decontamination of X-ray detector. Photostimulable phosphor plate

International Nuclear Information System (INIS)

Onuma, Yoji; Hayashi, Michiko; Hayashi, Hiroaki; Nishihara, Sadamitsu

2012-01-01

We tried to remove contamination of radioisotope (RI) for an X-ray detector (photostimulable phosphor plate; IP) and verified that our procedure suggested by Nishihara et al. was effective for decontamination. The procedure was as follows. First, the IP was kept for approximately twelve hours, and then it was processed [image (A)] as well as a clinical processing mode. Second, using a wet-type chemical wiper, we scavenged the IP to remove the adhered RI on its surface. Then, once again, the IP was kept for approximately fifteen hours and processed [image (B)] in order to check an effect of decontamination. Finally, the two images of (A) and (B) were analyzed using ImageJ, which can be downloaded as a free software, and a percentage of removal was calculated. The procedure was applied to two IPs using the Fuji computed tomography (FCR) 5501 plus. In the present case, the percentage of removal was approximately 96%. The removed radioisotopes in the chemical wipers were analyzed by Ge detector. Then, 134 Cs and 137 Cs were found with activities of 2.9 4.3 Bq and 3.5 5.2 Bq, respectively. For three months after that, we cannot see black spots on the IPs owing to the contamination of the RI and there are no defects caused by decontamination using a wet-type chemical wiper. (author)

Long-range transport of gaseous 131I and other radionuclides from Fukushima accident to Southern Poland

Science.gov (United States)

Mietelski, Jerzy W.; Kierepko, Renata; Brudecki, Kamil; Janowski, Paweł; Kleszcz, Krzysztof; Tomankiewicz, Ewa

2014-07-01

A serious accident at Fukushima Dai-Ichi NPP triggered radioactive emission to the atmosphere on 12 March 2011. The results of gamma spectrometric measurements of both gaseous and aerosol fraction of the air, collected in Krakow over the period from March 21 till the end of May 2011, as well as wet and dry deposition recorded from March till the end of October 2011, are presented in this paper. Krakow happened to be the first Polish location where radioactive isotopes characteristic for reactor releases, such as 131I, 132I, 129mTe, 132Te, 134Cs, 136Cs, and 137Cs, were detected. The maximum activity for aerosols equal to (5.73 ± 0.35) mBq/m3, (0.461 ± 0.041) mBq/m3 and (0.436 ± 0.038) mBq/m3 for 131I, 134Cs and 137Cs, respectively, was recorded for March 29, 2011. The data on the fallout are also given. The results of the radiochemical analysis of aerosol samples showed no traces of plutonium or americium isotopes associated with the disaster to be detected. The results of air activity concentration from Fukushima accident observed in Central Europe, Poland, in comparison to those of Chernobyl accident observed in Japan are presented and discussed. The comparison has revealed a discrepancy in the recognized relative scale of both accidents, and important difference in long distance transport of contamination, to exist. An attempt to explain the variation in the activity ratios between the aerosol fraction for 131I and 137Cs as resulting from exchange between the gaseous and aerosol fractions of 131I while the contamination had been propagating, is made.

Clinical evaluation of Proscillaridin-A with radioisotopes

International Nuclear Information System (INIS)

Franco, P.D.A.; Cordovil, I.L.; Rocha, A.F.G.

1976-01-01

Thirty patients with cardiac insufficiency were evaluated under the use of Proscillaridin-A. The analysis was based on classic clinical parameters and 11 patients through the circulation time with the radioisotopic technique. The results obtained are analysed and discussed about the absence of side effects, considering as well the therapeutic use of the drug [pt

Radiochemical determination of {sup 137}Cs in foods

Energy Technology Data Exchange (ETDEWEB)

Kastner, Geraldo F.; Ferreira, Andrea Vidal; Monteiro, Roberto P.G., E-mail: gfk@cdtn.br, E-mail: avf@cdtn.br, E-mail: rpgm@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

A determination of radionuclides in food samples is important in commodities in order to attend to regulatory requirements for international trade. As a long-lived radioisotope of cesium, {sup 137}Cs is produced as a result of human nuclear activities and than its contamination level evaluation among others radionuclides in foods is necessary. A methodology for the determination of {sup 137}Cs in foods, pork and fish, is described. The procedures covered homogenization and freeze-drying of the samples. The {sup 137}Cs was measured by gamma spectrometry using Canberra 50% HPGe detector. The counting was carried out with Monte Carlo software for detection conditions optimization including geometry and chemical data information. A certified sample, SRM IAEA-375, was analyzed in order to evaluate the reliability of the method, and the results showed good agreement between the measured and certified values. (author)

Labeling of Pest Insects Using Radioisotopes to Study Dispersal Pattern, Migration and Estimation of Population Density

International Nuclear Information System (INIS)

Singgih Sutrisno

2008-01-01

To study insects behaviour in their habitat such as dispersal, migration and flight range, insects are needed to be labelled to trace their movement. One of the most promising labeling methodology for internal labeling is the use of radioisotopes. Radioisotopes that have been used for labeling insects are 3 H, 32 P, 14 Ca, 45 K, 35 S, 59 Fe, 60 Co, and 14 C. Insect labeling with isotopes has more advantages as compared to dyes due to isotopes used for labeling is bonded to the tissue such as 3 H, 32 P, 14 Ca, K, 131 I. Several consideration have to be taken to determine isotopes that will be used in line with the time consuming for experiments. This have to be carried out due to the phenomenon that several isotopes are toxic to insects such as 45 Ca, 59 Fe, 86 Rb, 110 Ag, 115 Cd, and 131 J. Precautions have to be fulfilled for insect radiolabeling which are save to insects, environment, easy to apply, materials are available and acceptable to the public. Radioisotope 32 P with a correct dose is very convenience to be used in such experiments due to its relatively short half live, which is only 14.3 days. If it is an stable isotope it can be kept for a long time so the sample analyzed can be conducted convenience for long periods of time. Stable elements such as Rb can be changed to be radioisotopes by bombardment of neutrons in a nuclear reactor or accelerator. Then the element that has been activated can be identified using solid scintillation counter, multichannel analyzer or can be detected using autoradiography. (author)

Decontamination of radioisotope production facility

International Nuclear Information System (INIS)

Daryoko, M.; Yatim, S.; Suseno, H.; Wiratmo, M.

1998-01-01

The strippable coating method use phosphoric glycerol and irradiated latex as supporting agents have been investigated. The investigation used some decontaminating agents: EDTA, citric acid, oxalic acid and potassium permanganate were combined with phosphoric glycerol supporting agent, then EDTA Na 2 , sodium citric, sodium oxalic and potassium permanganate were combined with irradiated latex supporting agent. The study was needed to obtain the representative operating data, will be implemented to decontamination the Hot Cell for radioisotope production. The experiment used 50x50x1 mm stainless steel samples and contaminated by Cs-137 about 1.1x10 -3 μCi/cm 2 . This samples according to inner cover of Hot Cell material, and Hot Cell activities. The decontamination factor results of the investigation were: phosphoric glycerol as supporting agent, about 20 (EDTA as decontaminating agent) to 47 (oxalic acid as decontaminating agent), and irradiated latex as supporting agent, about 11.5 (without decontamination agent) to 27 (KMnO 4 as decontaminating agent). All composition of the investigation have been obtained the good results, and can be implemented for decontamination of Hot Cell for radioisotope production. The irradiated latex could be recommended as supporting agent without decontaminating agent, because it is very easy to operate and very cheap cost. (author)

Source of Iodine-131 in Europe Identified

International Nuclear Information System (INIS)

2011-01-01

Full text: The IAEA has received information from the Hungarian Atomic Energy Authority (HAEA) that the source of the iodine-131 (I-131) detected in Europe was most probably a release to the atmosphere from the Institute of Isotopes Ltd., Budapest. The Institute of Isotopes Ltd. produces radioisotopes for healthcare, research and industrial applications. According to the HAEA, the release occurred from September 8 to November 16, 2011. The cause of the release is under investigation. As previously mentioned, the levels of I-131 that have been detected in Europe are extremely low. There is no health concern to the population. If any member of the public were to breathe iodine for a whole year at the levels measured in European countries, then they would receive a dose in the range of 0.01 microsieverts for the year. To put this into perspective, the average annual background is 2 400 microsieverts per year. The IAEA was first notified of the presence of trace levels of I-131 by authorities from the Czech Republic on 11 November. Since this notification, the IAEA contacted several member states throughout the region to determine the cause and origin. The IAEA also worked with the World Meteorological Organization (WMO) to conduct air dispersion modelling, as part of efforts to determine the source. (IAEA)

The Influence of Antithyroid Drug Discontinuation to the Therapeutic Efficacy of 131I in Hyperthyroidism

International Nuclear Information System (INIS)

Kartamihardja, A. Hussein Sundawa; Massora, Stepanus

2016-01-01

The influence of antithyroid drugs (ATDs) on the therapeutic efficacy of radioactive iodine in hyperthyroidism is still controversial. The aim of this study was to evaluate the effect of ATD discontinuation to the therapeutic efficacy of I-131 in hyperthyroidism patients with long-term ATD treatment. Retrospective study was done to 39 subjects with hyperthyroidism who had been treated with doses of 300 MBq radioactive iodine. The subjects were divided into three groups: Group I (n = 14) had been using ATDs for more than one year and discontinued more than three days; group II (n = 14) had been using ATDs for more than one year but discontinued only for three days or less, and group III (n = 11) has never been used any ATD before radioactive iodine treatment. There was a significant difference in the therapeutic efficacy after three months of radioactive iodine treatment between group I and group II (P = 0.018), group II and group III (P = 0.017), but not between group I and group III (P = 1.0). There was no observed difference on the therapeutic efficacy between the three groups at 6 months after radioactive iodine therapy (P = 0.143). Administration of ATDs more than 1 year without discontinuation decreased response of radioactive iodine treatment in 3 months follow-up. Discontinuation of ATDs for more than 3 days before radioactive iodine treatment is recommended

The Influence of Antithyroid Drug Discontinuation to the Therapeutic Efficacy of (131)I in Hyperthyroidism.

Science.gov (United States)

Kartamihardja, A Hussein Sundawa; Massora, Stepanus

2016-01-01

The influence of antithyroid drugs (ATDs) on the therapeutic efficacy of radioactive iodine in hyperthyroidism is still controversial. The aim of this study was to evaluate the effect of ATD discontinuation to the therapeutic efficacy of I-131 in hyperthyroidism patients with long-term ATD treatment. Retrospective study was done to 39 subjects with hyperthyroidism who had been treated with doses of 300 MBq radioactive iodine. The subjects were divided into three groups: Group I (n = 14) had been using ATDs for more than one year and discontinued more than three days; group II (n = 14) had been using ATDs for more than one year but discontinued only for three days or less, and group III (n = 11) has never been used any ATD before radioactive iodine treatment. There was a significant difference in the therapeutic efficacy after three months of radioactive iodine treatment between group I and group II (P = 0.018), group II and group III (P = 0.017), but not between group I and group III (P = 1.0). There was no observed difference on the therapeutic efficacy between the three groups at 6 months after radioactive iodine therapy (P = 0.143). Administration of ATDs more than 1 year without discontinuation decreased response of radioactive iodine treatment in 3 months follow-up. Discontinuation of ATDs for more than 3 days before radioactive iodine treatment is recommended.

The Influence of Antithyroid Drug Discontinuation to the Therapeutic Efficacy of 131I in Hyperthyroidism

Science.gov (United States)

Kartamihardja, A. Hussein Sundawa; Massora, Stepanus

2016-01-01

The influence of antithyroid drugs (ATDs) on the therapeutic efficacy of radioactive iodine in hyperthyroidism is still controversial. The aim of this study was to evaluate the effect of ATD discontinuation to the therapeutic efficacy of I-131 in hyperthyroidism patients with long-term ATD treatment. Retrospective study was done to 39 subjects with hyperthyroidism who had been treated with doses of 300 MBq radioactive iodine. The subjects were divided into three groups: Group I (n = 14) had been using ATDs for more than one year and discontinued more than three days; group II (n = 14) had been using ATDs for more than one year but discontinued only for three days or less, and group III (n = 11) has never been used any ATD before radioactive iodine treatment. There was a significant difference in the therapeutic efficacy after three months of radioactive iodine treatment between group I and group II (P = 0.018), group II and group III (P = 0.017), but not between group I and group III (P = 1.0). There was no observed difference on the therapeutic efficacy between the three groups at 6 months after radioactive iodine therapy (P = 0.143). Administration of ATDs more than 1 year without discontinuation decreased response of radioactive iodine treatment in 3 months follow-up. Discontinuation of ATDs for more than 3 days before radioactive iodine treatment is recommended. PMID:27134556

Medically-derived I-131: a potential tool for understanding the fate of wastewater nitrogen in aquatic systems

Science.gov (United States)

Rose, P. S.; Smith, J. P.; Aller, R. C.; Cochran, J. K.; Swanson, R. L.; Murthy, S. N.; Coffin, R. B.

2010-12-01

Iodine-131(t1/2 = 8 days) has been measured in Potomac River water and sediments in the vicinity of the Blue Plains Water Pollution Control Plant (WPCP), Washington, DC. The source of I-131 is medical, where it is commonly used to treat thyroid cancer and hyperthyroidism. Iodine is metabolized by patients and eliminated primarily in urine. While other medical radioisotopes may enter the environment via sewage effluent, the nature and quantity of treatments using I-131 cause it to account for much of the radioactivity in sewage effluent. Natural iodine in aquatic systems is biologically cycled similar to other nutrients, such as nitrogen. Iodine-131 concentrations measured in sewage effluent from Blue Plains WPCP and in the Potomac River suggest a relatively continuous discharge of this isotope. Dissolved I-131 shows a strong, positive correlation with δ15N values of nitrate in the river. The range of I-131 concentrations detected in surface waters is 0.18 ± 0.01 to 0.68 ± 0.02 Bq/L. Surface water δ15NO3 values ranged from 8.7 ± 0.3 to 33.4 ± 7.3 ‰ with NO3+NO2 concentrations between 0.38 ± 0.02 and 2.79 ± 0.13 mgN/L. Sediment profiles of particulate I-131 and δ15N indicate rapid mixing or sedimentation and in many cases remineralization of a heavy nitrogen source consistent with wastewater nitrogen. Iodine-131 concentrations in sediments ranged from 1.31 ± 0.8 to 117 ± 2 Bq/kg dry weight. Values of δ15N in sediments ranged from 4.7 ± 0.1 ‰ to 9.3 ± 0.1 ‰. We propose that I-131 coupled with δ15N can be an excellent tracer for the short-term fate of wastewater nitrogen in this system. However, the utility of I-131 as a tracer is not limited to use in the Potomac River. Other studies have documented the presence of I-131 in several aquatic systems and continuous discharges of this radioisotope in sewage effluent are likely to be widespread in urban environments.

Optimization of the therapeutic dose of {sup 131}I for thyroid differentiated carcinoma; Otimizacao da dose terapeutica com {sup 131}I para carcinoma diferenciado da tiroide

Energy Technology Data Exchange (ETDEWEB)

Lima, Fabiana Farias de

2002-09-01

reduction for many organs, such as the narrow and gonads, of up to 78.4%.Possible benefits to the institution also include the use of less radioactive material and a reduction in radiation exposures to the staff during the manipulation and administration of the {sup 131} I. To facilitate the calculations of the optimum therapeutic activity of {sup 131} I for individual patients, a simple and fast dose planning program was created (PlanDose). The program has been set up to evaluate thryroid remant ablation, but it can also be used for the calculation of the activity to be administered for treatment of hyperthyroidism. This protocol of calculated optimal patient-specific {sup 131} I. activities allows a better determination of the necessary ablative dose for patients with differentiated carcinoma of the thyroid, and is an example of optimizing the practice of radiation protection. (author)

Alteration of radioactive iodine uptake after treatment of hyperthyroidism with iodine 131

International Nuclear Information System (INIS)

Heath, R.C.; Gossain, V.V.; Rovner, D.R.

1988-01-01

To determine whether a therapeutic dose of iodine 131 affects the results of 24-hour radioactive iodine uptake (RAIU) testing, we reviewed records of hyperthyroid patients previously treated with 131 I at Michigan State University and its affiliated hospitals. We identified 26 patients who had had clinical evaluation and determination of the serum thyroxine (T4) level, triiodothyronine resin uptake (T3RU), and RAIU (using 131 I) within two weeks before and several months after the therapeutic dose of 131 I. Before treatment, all patients had clinical hyperthyroidism, with an elevated T4 level and increased T3RU and RAIU. After treatment with 131 I, eight patients (31%) had an RAIU that was discordant with their clinical and biochemical (T4 and T3RU) assessment. In six patients (23%) of the RAIU was inappropriately high, and in two patients (8%) it was inappropriately low. Since we did not identify any other factors known to interfere with the results of RAIU testing, we conclude that a therapeutic dose of 131 I, may by itself increase or decrease a subsequent RAIU determination; therefore, after treatment with 131 I, RAIU is not a good diagnostic index of thyroid activity

Cancer risk due to Cs-137 and Sr-90 dietary intake after the Chernobyl accident

International Nuclear Information System (INIS)

Toader, M.; Vasilache, R.A.

1997-01-01

The most important radionuclides carried by the radioactive plume over Romania were I 131 , Cs 134 , Cs 137 and Sr 90 . As in many other countries, in the first days, I 131 had the main contribution to the irradiation dose released to the population. After its decay, and the decay of the other short-lived radionuclides, Cs 137 and Sr 90 remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. Assessments of radiation doses to people living in the Bucharest area have utilized data obtained from measurement of Cs 137 and Sr 90 content in dietary intake samples for a number of subjects of different ages and sexes. This paper summarizes the results of some of our measurements performed since April 1986 until March 1995. 7 refs, 8 figs

Transport of radioisotopes

International Nuclear Information System (INIS)

Aoki, Shigefumi

1978-01-01

Presently the amount of radioisotopes increased very much and the application spread to wide fields in Japan. Since facilities using radioisotopes are distributed to every place in the country, every transport means such as airplanes, automobiles, railways, ships and mail are employed. The problems in the transport of radioisotopes include too much difference in the recognition of criticality among the persons concerning the transportation and treatment, knowledges of shielding and energy difference in the types of radiation and handling of sealed and unsealed sources and the casks for transport. IAEA established the latest regulation on the package of radioisotopes in 1973, and in Japan, the related regulations will be revised according to the IAEA's regulation in near future. The present status in the inspection at the time of shipment, supervision, and the measures to the accidents are described for the transport means of airplanes, ships and automobiles. Finally, concerning the insurance for cargo, the objects of the insurance for radioisotopes include either the radioisotopes contained in casks for transportation or radioisotopes only. Generally, radioisotopes are accepted in all-risk condition including casks and limited to the useful radioisotopes for peaceful use. (Wakatsuki, Y

Synthesis and In Vitro and In Vivo Evaluation of Iodine-131-Labeled Folates: Potential Molecular Diagnostic and Therapeutic Radiopharmaceuticals

International Nuclear Information System (INIS)

Al Jammaz, I.

2009-01-01

Molecular targeting imaging has a great potential to be able to image molecular changes that are currently defined as predisease states which facilitate earlier detection of cancer and consequently, the greatest chance of cure. Advancement of scintigraphic imaging and radiotherapy is highly determined by development of more specific radiotracers. The Membrane-associated-folic acid receptor is a glycosylphospstidylinositol protein that overexpressed in approximately 100% of serious ovarian adenocarcinomas and various epithelial cancers including cervical, colorectal and renal cancers. Meanwhile, this receptor is highly restricted in most normal tissues which make these tumors as an excellent candidates for molecular targeting imaging and therapy through the folate receptor system. As part of our on-going research effort to develop prosthetic precursors for radiohalogenation of bioactive molecules, we have previously reported the synthesis and biological characterization of [ 18 F]- fluorobenzene and pyridine carbohydrazide-folate conjugates ([ 18 F]-SFB and [ 18 F]-SFP-folates). We here report the synthesis and biological characterization of [ 131 I]-iodobenzenecarbohydrazide-folate conjugate ([ 131 I]-SIB-folate) as a potential therapeutic radiopharmaceutical. The synthetic approaches for preparation of [ 131 I]iodobenzene carbohydrazide-folates ([ 131 I]-SIB-folate) entailed sequence of reactions. Hydrazide-folate was reacted with N-succinimidyl-m-[131I]-iodobenzoate-carboxylate ([ 131 I]-SIB) to give [ 131 I]-SIB-folate conjugate. Radiochemical yield was greater than 80% and synthesis times were ranging between 40-45 min. Radiochemical purity was also greater than 97% without HPLC purification. These synthetic approaches hold considerable promise as rapid and simple method for the radiohalogenation of folate in high radiochemical yield in short time. In vitro tests on KB cell line has shown that significant amount of the radioconjugate associated with cell

Preparation of [[sup 131]I]lipiodol as a hepatoma therapeutic agent

Energy Technology Data Exchange (ETDEWEB)

Jiunnguang Lo; Aiyih Wang; Yuanyaw Wei (National Tsinghua Univ., Hsinchu (Taiwan). Inst. of Nuclear Science); Wingyiu Lui; Chinwen Chi (Taipei Veterans General Hospital, Taipei (Taiwan)); Wingkai Chan (Academia Sinica, Taipei (Taiwan). Inst. of Biomedical Sciences)

1992-12-01

An isotopic exchange method was used to label lipiodol with [sup 131]I. The labelling efficiency was > 92.5%, and the radiochemical purity of [[sup 131]I]lipiodol was above 98% as determined by ITLC. The influencing factors e.g. the heating temperature, reaction, pH and storage conditions were studied and the optimum conditions were determined. In a pilot study injecting [[sup 131]I]lipiodol for the treatment of hepatoma, about 70% of hepatoma patients had a response to the treatment with a reduction of [alpha]-fetoprotein and decrease of hepatoma sizes. The overall median survival was 9 months (range 2-17 months). (author).

Evaluation of Cs-134 and Cs-137 in sugar by non-destructive analysis

Energy Technology Data Exchange (ETDEWEB)

Correira, Filipe Lopes de Barros; Santos Júnior, José Araújo dos; Amaral, Romilton dos Santos; Santos, Josineide Marques do Nascimento; Medeiros, Nilson Vicente da Silva; Santos Junior, Otávio Pereira dos, E-mail: filipelbck@gmail.com, E-mail: jaraujo@ufpe.br, E-mail: romilton@ufpe.br, E-mail: josineide.santos@ufpe.br, E-mail: nilson.medeiros@ufpe.br, E-mail: otavio.santos@vitoria.ifpe.edu.br [Universidade Federal de Pernambuco (RAE/UFPE), Recife, PE (Brazil). Departamento de Energia Nuclear. Grupo de Radioecologia; Vieira, José Wilson, E-mail: jose.wilson59@uol.com.br [Instituto Federal de Pernambuco (IFPE), Recife (Brazil); Valois, Rhaiana Caminha, E-mail: rhaianavalois@hotmail.com [Colégio Militar do Recife, PE (Brazil)

2017-07-01

The spread of anthropogenic radioisotopes in the environment comes from nuclear tests and accidents that occurred in the past, which justifies constant monitoring, to guarantee the safety and control of the activities that involve these applications. Brazil, when exporting some food products, depending on the country of origin, a radiometric report is required, especially for sugar that has high world consumption and the possibility of contamination of the population, when radioisotope is present. Therefore, the investigation of the levels of Cs-134 and Cs-137 in sugar matrices is necessary to predict radioecological emergency situations. The National Nuclear Energy Commission, the agency that oversees nuclear applications in Brazil, With Resolution No. 102 of December 22, 2010 approved regulatory positions, including levels of action for food control, recommended to restrict the marketing of food products in Brazil. General, whose specific activity is higher than the limit of 1.0 kBq / kg for the said isotopes of cesium independently. Aiming for improvements in the analyzes that are already performed in the Laboratory of Radioecology and Environmental Control of the Department of Nuclear Energy of the Federal University of Pernambuco to assurance the quality of sugar marketed in Brazil, a standard procedure for the analysis of these radionuclides in this matrix was determined. High resolution gamma spectrometry with non-destructive analysis was used to perform the tests. Priority was given to parameters that directly influence the qualitative and quantitative analysis of these radioactive elements, such as calibration in energy and efficiency, resolution, influence of self-absorption, counting statistics directly associated with the time of analysis, influence of background radiation and geometry analysis. (author)

Evaluation of Cs-134 and Cs-137 in sugar by non-destructive analysis

International Nuclear Information System (INIS)

Correira, Filipe Lopes de Barros; Santos Júnior, José Araújo dos; Amaral, Romilton dos Santos; Santos, Josineide Marques do Nascimento; Medeiros, Nilson Vicente da Silva; Santos Junior, Otávio Pereira dos; Valois, Rhaiana Caminha

2017-01-01

The spread of anthropogenic radioisotopes in the environment comes from nuclear tests and accidents that occurred in the past, which justifies constant monitoring, to guarantee the safety and control of the activities that involve these applications. Brazil, when exporting some food products, depending on the country of origin, a radiometric report is required, especially for sugar that has high world consumption and the possibility of contamination of the population, when radioisotope is present. Therefore, the investigation of the levels of Cs-134 and Cs-137 in sugar matrices is necessary to predict radioecological emergency situations. The National Nuclear Energy Commission, the agency that oversees nuclear applications in Brazil, With Resolution No. 102 of December 22, 2010 approved regulatory positions, including levels of action for food control, recommended to restrict the marketing of food products in Brazil. General, whose specific activity is higher than the limit of 1.0 kBq / kg for the said isotopes of cesium independently. Aiming for improvements in the analyzes that are already performed in the Laboratory of Radioecology and Environmental Control of the Department of Nuclear Energy of the Federal University of Pernambuco to assurance the quality of sugar marketed in Brazil, a standard procedure for the analysis of these radionuclides in this matrix was determined. High resolution gamma spectrometry with non-destructive analysis was used to perform the tests. Priority was given to parameters that directly influence the qualitative and quantitative analysis of these radioactive elements, such as calibration in energy and efficiency, resolution, influence of self-absorption, counting statistics directly associated with the time of analysis, influence of background radiation and geometry analysis. (author)

Preliminary studies of Brazilian wood using different radioisotopic sources

International Nuclear Information System (INIS)

Carvalho, Gilberto; Silva, Leonardo Gondim de Andrade e

2013-01-01

Due to availability and particular features, wood was one of the first materials used by mankind with a wide variety of applications. It can be used as raw material for paper and cellulose manufacturing; in industries such as chemical, naval, furniture, sports goods, toys, and musical instrument; in building construction and in the distribution of electric energy. Wood has been widely researched; therefore, wood researchers know that several aspects such as temperature, latitude, longitude, altitude, sunlight, soil, and rainfall index interfere with the growth of trees. This behavior explains why average physical-chemical properties are important when wood is studied. The majority of researchers consider density to be the most important wood property because of its straight relationship with the physical and mechanical properties of wood. There are three types of wood density: basic, apparent and green. The apparent density was used here at 12% of moisture content. In this study, four different types of wood were used: 'freijo', 'jequetiba', 'muiracatiara' and 'ipe'. For wood density determination by non-conventional method, Am-241, Ba-133 and Cs-137 radioisotopic sources; a NaI scintillation detector and a counter were used. The results demonstrated this technique to be quick and accurate. By considering the nuclear parameters obtained as half value layers and linear absorption coefficients, Cs-137 radioisotopic source demonstrated to be the best option to be used for inspection of the physical integrity of electric wooden poles and live trees for future works. (author)

Effect of 137Cs on immunological reactivity

International Nuclear Information System (INIS)

Shubik, V.M.

1975-01-01

An important role of 137 Cs as a new ecological factor was shown by analyzing 31 different studies. The radioisotope may at present be detected in the organisms of all inhabitants of this planet. The migration of 137 Cs along the chain lichen-deer-man leads to its accumulation in the organism of humans living in the Extreme North and taking venison in their food. Although the high sensitivity of immunological reactions to various unfavourable environmental factors is well known, data on the effect of incorporated 137 Cs on immunity are scanty. Experiments on animals showed changes in factors of nonspecific immunity (phagocytic reaction of blood neutrophils, bactericidal activity, lysozyme and complement titres of blood serum) and specific immunity (formation of antiviral antibodies). The blood of animals injured by the isotope displays complete and incomplete autoantibodies. The dependence of immunobiological changes on the dose absorbed by the organism is shown. The 137 Cs intake of inhabitants of the Extreme North who eat venison did not, with the absorbed dose equalling up to 50 Mrem per year, lead to changes in their immunological reactivity. (author)

US Department of Energy radioisotope customers with summary of radioisotope shipments, FY 1988

International Nuclear Information System (INIS)

Van Houten, N.C.

1989-06-01

Pacific Northwest Laboratory (PNL) prepared this edition of the radioisotope customer list at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, US Department of Energy (DOE). This is the 25th report in a series dating from 1964. This report covers DOE radioisotope sales and distribution activities by its facilities to domestic, foreign and other DOE facilities for FY 1988. The report is divided into five sections: radioisotope suppliers, facility contacts, and radioisotopes or services supplied; a list of customers, suppliers, and radioisotopes purchased; a list of radioisotopes purchased cross-referenced to customer numbers; geographic locations of radioisotope customers; and radioisotope sales and transfers -- FY 1988. Radioisotopes not previously reported in this series of reports were argon-37, arsenic-72, arsenic-73, bismuth-207, gadolinium-151, rhenium-188, rhodium-101, selenium-72, xenon-123 and zirconium-88. The total value of DOE radioisotope sales for FY 1988 was $11.1 million, an increase of 3% from FY 1987

US Department of Energy radioisotope customers with summary of radioisotope shipments, FY 1988

Energy Technology Data Exchange (ETDEWEB)

Van Houten, N.C.

1989-06-01

Pacific Northwest Laboratory (PNL) prepared this edition of the radioisotope customer list at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, US Department of Energy (DOE). This is the 25th report in a series dating from 1964. This report covers DOE radioisotope sales and distribution activities by its facilities to domestic, foreign and other DOE facilities for FY 1988. The report is divided into five sections: radioisotope suppliers, facility contacts, and radioisotopes or services supplied; a list of customers, suppliers, and radioisotopes purchased; a list of radioisotopes purchased cross-referenced to customer numbers; geographic locations of radioisotope customers; and radioisotope sales and transfers -- FY 1988. Radioisotopes not previously reported in this series of reports were argon-37, arsenic-72, arsenic-73, bismuth-207, gadolinium-151, rhenium-188, rhodium-101, selenium-72, xenon-123 and zirconium-88. The total value of DOE radioisotope sales for FY 1988 was $11.1 million, an increase of 3% from FY 1987.

Radiological Risk for Patients Treated with 131I

International Nuclear Information System (INIS)

Chas, J.; Janiak, M.K.; Kowalczyk, A.; Siekierzynski, M.; Dziuk, E.

2001-01-01

Full text: Dose equivalents were measured during the three-day therapy with 131 I in patients treated at the Clinic of Endocrinology and Radioisotope Therapy, Central Clinical Hospital, Military University School of Medicine, Warsaw, Poland, for thyroid cancer (supplementary treatment; 21 cases), hyperthyroidism in the Graves-Basedov's disease (18 cases), and toxic nodular goiter (19 cases). The absorbed doses were measured with thermoluminescent dosimeters placed above the jugular incisure and above the pubic symphysis; the readings were used for calculation of the dose equivalent over the thyroid and in the ovaries. Following the radical treatment of thyroid cancer iodine uptake in the thyroid gland was very low and most of the applied 131 I was excreted within one to three days. In our 21 patients who were given on average 2.8 GBq (76 mCi) 131 I and stimulated with TSH (approx. 60 μIU/mL) the mean dose equivalents over the thyroid and in the ovaries were 115±123 mSv and 56±19 mSv, respectively. In comparison, the calculated dose equivalents in the Graves-Basedov's disease patients (424 MBq mean activity of the applied 131 I) and the goiter patients (544 MBq mean activity of the applied 131 I) were approx. 3.5 times higher over the thyroid and approx. 2.5 times lower in the ovaries. No disfunctions of the ovaries were detected in the treated young women. Based on these results it is recommended to stimulate diuresis during the first two-three days after the injection of 131 I. The results also indicate that exposure to ionising radiation of patients treated for various thyroid disorders with 131 I does not lead to the development of clinically detectable non-stochastic effects. (author)

Effect of 131I therapy on outcomes of Graves' ophthalmopathy

International Nuclear Information System (INIS)

Wang Renfei; Tan Jian; Zhang Guizhi; Yin Liang

2011-01-01

Objective: To analyze the correlation between the therapeutic effect of Graves' hyperthyroidism and the outcomes of Graves' ophthalmopathy after 131 I therapy, and to explore the effect of 131 I treatment on turnout of Graves' ophthalmopathy. Methods: Six hundreds and fifty-two patients of Graves' disease accompanied with Graves' ophthalmopathy, received one-time 131 I treatment according to routine procedure. We recorded exophthalmometer readings, the signs and symptoms of eyes before therapy. Regular follow-up and appraisal of curative effect were carried out. Results: At least six months after 131 I therapy, the effective rate of Graves' hyperthyroidism and Graves' ophthalmopathy were 94.3% and 73.3% respectively. The total effective rate of hyperthyroidism with ophthalmopathy was 71.2%. There was a significant correlation between the prognosis of Graves' ophthalmopathy and therapeutic efficacy of hyperthyroidism (r=0.302, P 131 I therapy (χ 2 =0.296, P>0.05). Conclusions: The key to treat Graves' ophthalmopathy is the cure of Graves' hyperthyroidism through 131 I therapy. The timely diagnosis and replacement treatment of hypothyroidism can effectively avoid the aggravation of Graves' ophthalmopathy after 131 I therapy. (authors)

Development of real-time radioisotope imaging system to study plant nutrition

International Nuclear Information System (INIS)

Nakanishi, Tomoko M.; Kobayashi, Natsuko I.; Hirose, Atsushi; Saito, Takayuki; Sugita, Ryohei; Tanoi, Keitaro; Suzuki, Hisashi; Iwata, Ren

2013-01-01

We have been developing two types of realtime radioisotope imaging systems, one for macroscopic imaging targeting the whole plant itself and the other for microscopic imaging under modified fulorescent microscope to get both fluorescent and radioisotope images (Hirose et al. 2012; Kanno et al. 2012; Kobayashi et al. 2012). Now we can visualize the realtime movement of C-14, Na-22, Mg-28, P-32, S-35, K- 42, Ca-45, Rb-86 or Cs-137, from root kept in dark to up-ground part where light was irradiated. There are a wide range of application of this imaging, such as to measure the uptake manner in root, speed or distribution or translocation manner, as well as distribution, translocation or deposition of the nutrient element in upground part. Here we present some representative real-time images in plants. (author)

Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department`s mission as stated in that document. ``The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.``

Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

International Nuclear Information System (INIS)

1995-10-01

The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department's mission as stated in that document. ''The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.''

Clinical applications of radioiodine 131 (I131) in the thyroid diseases

International Nuclear Information System (INIS)

Gonzalez Rivero, Levi; Turcios Trista, Silvia Elena; Velasco Mirabal, Milagros

2012-01-01

Radioiodine 131 is a radioactive isotope that is successfully used for the diagnosis and the treatment of benign and malignant thyroid diseases. Its quality of selectively integrating to the thyroid metabolism and emitting a signal allows it to describe the gland functioning through capture studies, and to delimit the morphology and location of the tissues that capture iodine by means of scintigraphy. It is also a simple, safe and cost-effective radiotherapy used as first-line therapeutics in the control of hyperthyroidism. The dose and right time of application should be individualized according to the etiology and the clinic of each patient. Radioiodine 131 offers an efficient alternative to reduce the size of non-toxic goiter in addition to supporting the surgical treatment of the differentiated thyroid carcinoma and destroying with ablative doses the tissular remains and the metastatic lesions that can be detected during the gammagraphic follow-up. Radioiodine 131 depends on the fulfillment of safety regulations against radioactivity

Clinical applications of radioiodine 131 (I131) in the thyroid diseases

International Nuclear Information System (INIS)

Gonzalez, Rivero Levi; Turcios Trista, Silvia Elena; Velasco Mirabal, Milagros

2012-01-01

Radioiodine 131 is a radioactive isotope that is successfully used for the diagnosis and the treatment of benign and malignant thyroid diseases. Its quality of selectively integrating to the thyroid metabolism and emitting a signal allows it to describe the gland functioning through capture studies, and to delimit the morphology and location of the tissues that capture iodine by means of gammagraphy. It is also a simple, safe and cost-effective radiotherapy used as first-line therapeutics in the control of hyperthyroidism. The dose and right time of application should be individualized according to the etiology and the clinic of each patient. Radioiodine 131 offers an efficient alternative to reduce the size of non-toxic goiter in addition to supporting the surgical treatment of the differentiated thyroid carcinoma and destroying with ablative doses the tissular remains and the metastatic lesions that can be detected during the gammagraphic follow-up. Radioiodine 131 depends on the fulfillment of safety regulations against radioactivity

Adsorption of Cs-137 and U-238 in semi-arid soils; Adsorcion de Cs-137 y U-238 en suelos semiaridos

Energy Technology Data Exchange (ETDEWEB)

Hernandez T, U. O. [Instituto Tecnologico de Toluca, Av. Tecnologico s/n, 52140 Metepec, Estado de Mexico (Mexico); Monroy G, F.; Anguiano A, J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Fernandez R, E., E-mail: uohtrejo@gmail.com [Universidad Politecnica del Valle de Toluca, Carretera Toluca-Almoloya de Juarez Km. 5.6, Santiaguito Tlalcilalcali, Estado de Mexico (Mexico)

2013-10-15

Is of great importance to determine the adsorption properties of the soils where radioactive wastes are stored, fundamentally of the radioisotopes contained in these wastes, with the purpose of knowing like will be their behavior in the event of happening radionuclide migration toward the surrounding means. Therefore, in this work the adsorption properties of {sup 137}Cs{sup +} and {sup 238}UO{sub 2}{sup 2+} in soils coming from the Storage Center of Radioactive Wastes are studied. Was studied the effect of the soil type and the particle size of the soil in the adsorption properties of Cs (I) and U (Vi). 13 soil samples and six different particle sizes were analyzed. The adsorption studies were carried out by the radiotracers technique in static way. The results indicate an important adsorption affinity toward the Cs-137 and a very vulnerable affinity for the {sup 238}UO{sub 2}{sup 2+}. (author)

Status and prospects on radioisotope production in Korea

International Nuclear Information System (INIS)

Han, H. S.; Cho, W. K.; Park, U. J.; Hong, Y. D.; Park, K. B.

2002-01-01

In Korea, radioisotopes has been produced using small-sized research reactors (TRIGA Mark II, III) from 1961 to 1995. The Korea Atomic Energy Research Institute (KAERI) completed the High-flux Advanced Neutron Application Reactor (HANARO) in 1995 and a radioisotope production facilities (RIPF) in 1997. Medical and industrial radionuclides such as 131 I, 99m Tc, 166 Ho, 192 Ir and 60 Co, are routinely produced utilizing HANARO. Several hundreds kilo curies of these nuclides were supplied to domestic users in 2001. The Korea Cancer Center Hospital (KCCH) first installed a cyclotron (MC-50) for neutron therapy and RI production in 1984. At present, the cyclotron routinely produced radionuclides such as 201 TI, 67 Ga, 123 I and 18 F. Also, it is capable of producing several radionuclides, including 111 In, 51 Cr, 124 I, 54 Mn, 22 Na, etc. Baby cyclotrons were installed in Seoul National University Hospital, Sam sung Medical Center and Asan Medical Center. The main purpose of the introduction of baby cyclotrons was to produce short-lived positron emitters such as 18 F, 15 O and 11 C for PET. Radioisotope production facilities were imported and installed as subsidiaries of cyclotron. In Korea, more than 60 kinds of radioisotopes are currently used in the field of their applications and most of them are imported form foreign vendors. For the quality assurance of final products such as radiopharmaceuticals and industrial sources, facilities for production should be installed and maintained in accordance with regulation rules and also the production system should be operated under quality management system. Since 1992 the Korean government has been encouraging Mid and Long Term Nuclear R and D Programs to enhance capability in nuclear technology development. In order to actively promote the utilization, research and development of technology applying radiation and RI, the Korean government established 'a comprehensive promotion plan for utilization, research and development

Technical Reviews on the Radioisotope Application for Leak Detection in Reservoirs

International Nuclear Information System (INIS)

Kim, Jin Seop; Jung, Sung Hee; Kim, Jong Bum; Kim, Jae Ho

2006-02-01

The previous techniques on the detection of leaks from reservoirs are difficult to identify the leak points and leak pathways in reservoirs. Additionally the complexity and ambiguity of data analysis resulted from them can increase the failures of leak detection. While, The technique using radioisotope as a tracer is considered to be very promising. In the same context, systematic studies led by IAEA are being practiced by organizing the task force team. The detection technique using natural tracer can give information about the age of ground water and the interconnection between ground water and reservoir water and the seepage origin. On the other hand, the one using artificial tracer can identify the leak point in reservoirs directly, in which radioactive cloud migration method and radioactive tracer adsorption method are included. The former is using hydrophilic radioisotope tracer, and the latter adsorptive radioisotope tracer which is emitting gamma ray. The radiotracer are injected at a point of the reservoir near to the bottom. Afterwards, the migration of the radioactive tracer is followed by means of submerged scintillation detectors suspended from boats. Usually 131 I, 82 Br, 46 Sc, and 198 Au etc. can be used as tracer. The point reaching the maximum concentration of tracer corresponds to the leak point in reservoirs

Technical Reviews on the Radioisotope Application for Leak Detection in Reservoirs

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Seop; Jung, Sung Hee; Kim, Jong Bum; Kim, Jae Ho

2006-02-15

The previous techniques on the detection of leaks from reservoirs are difficult to identify the leak points and leak pathways in reservoirs. Additionally the complexity and ambiguity of data analysis resulted from them can increase the failures of leak detection. While, The technique using radioisotope as a tracer is considered to be very promising. In the same context, systematic studies led by IAEA are being practiced by organizing the task force team. The detection technique using natural tracer can give information about the age of ground water and the interconnection between ground water and reservoir water and the seepage origin. On the other hand, the one using artificial tracer can identify the leak point in reservoirs directly, in which radioactive cloud migration method and radioactive tracer adsorption method are included. The former is using hydrophilic radioisotope tracer, and the latter adsorptive radioisotope tracer which is emitting gamma ray. The radiotracer are injected at a point of the reservoir near to the bottom. Afterwards, the migration of the radioactive tracer is followed by means of submerged scintillation detectors suspended from boats. Usually {sup 131}I, {sup 82}Br, {sup 46}Sc, and {sup 198}Au etc. can be used as tracer. The point reaching the maximum concentration of tracer corresponds to the leak point in reservoirs.

Cancer risk due to Cs-137 and Sr-90 dietary intake after the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Toader, M; Vasilache, R A [Institute of Hygiene and Public Health, Bucharest (Romania)

1997-09-01

The most important radionuclides carried by the radioactive plume over Romania were I{sup 131}, Cs{sup 134}, Cs{sup 137} and Sr{sup 90}. As in many other countries, in the first days, I{sup 131} had the main contribution to the irradiation dose released to the population. After its decay, and the decay of the other short-lived radionuclides, Cs{sup 137} and Sr{sup 90} remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. Assessments of radiation doses to people living in the Bucharest area have utilized data obtained from measurement of Cs{sup 137} and Sr{sup 90} content in dietary intake samples for a number of subjects of different ages and sexes. This paper summarizes the results of some of our measurements performed since April 1986 until March 1995. 7 refs, 8 figs.

Analysis of 131I therapy in 71 patients with hyperthyroidism

International Nuclear Information System (INIS)

Wang Ping; Chen Zequan; Wang Yuanzhi; Ye Shiqing

2001-01-01

Objective: To evaluate the clinical significance of iodine-131 treatment in patients with hyperthyroidism. Methods: The dose of 131 I was determined according to thyroid absorption of 131 I at 24 hrs post administration and thyroid weight estimated in ECT examination. Results: One dose cure rate of 131 I treatment was 96% (68/71). Hypothyroidism occurred in 3 of 71 patients (4%) in one year after administration. No other serious complication was observed. Conclusion: The therapeutic effect of 131 I in treating hyperthyroidism was quite encouraging. The administration regime was also simple

Effect of mycorrhizal infection on root uptake by pine seedlings and redistribution of three contrasting radio-isotopes: {sup 85}Sr, {sup 95m}Tc and {sup 137}Cs

Energy Technology Data Exchange (ETDEWEB)

Plassard, C.; Ladeyn, I.; Staunton, S. [Institut National de Recherches Agronomiques (INRA), UMR Rhizosphere and Symbiose 34 - Montpellier (France)

2004-07-01

Mycorrhizal infection is known to improve phosphate nutrition and water supply of higher plants. It has been reported to both increase the uptake of potentially toxic pollutant elements and to protect plants against toxic effects. Little is known about the effect of mycorrhizal infection on the dynamics of radioactive pollutants in soil-plant systems. The aim of this study was to compare the root uptake and root-shoot transfer of three radio-isotopes with contrasting chemical properties ({sup 85}Sr, {sup 95m}Tc and {sup 137}Cs) in mycorrhizal and control, non mycorrhizal plants. The plant studied was Pinus pinaster and the associated ecto-mycorrhizal fungus was Rhizopogon roseolus (strain R18-2). Plants were grown under anoxic conditions for 3 months then transferred to thin layers of autoclaved soil and allowed to grow for four months. After this period, the rhizotrons were dismantled, and plant tissue analysed. Biomass, nutrient content (K, P, N, Ca) and activities of each isotope in roots, shoots and stems were measured, and the degree of mycorrhizal infection assessed. The transfer factors decreased in the order Tc>Sr>Cs as expected from the degree of immobilisation by soil. No effect of mycorrhizal infection on root uptake was observed for Sr. Shoot activity concentration of Tc was decreased by mycorrhizal infection but root uptake correlated well with mycelial soil surface area. In contrast, Cs shoot activity was greater in mycorrhizal than control plants. The uptake and root to shoot distribution shall be discussed in relation to nutrient dynamics. (author)

Radioisotopes production and applications

International Nuclear Information System (INIS)

Dash, Ashutosh

2015-01-01

Application of radioisotopes for both medical and industrial applications constitutes one of the most important peaceful uses of atomic energy. The striking diffusion and the exciting perspective of radioisotope for a plethora of medical and industrial applications are mainly attributable to the penetrating and ionization properties of radiation emanating from radioisotopes. The revolutionary medical applications of radioisotopes for the diagnosis and treatment of a multitude of diseases are causing a rapid expansion of the nuclear medicine field. While the industrial uses of radioisotopes are not expanding as quickly, also require large amounts of radioisotopes. Production of radioisotopes is not only the first step, but also the most crucial for the success as well as sustainable growth of radioisotope applications. With the rapid growth and expanding areas of applications, the demands for isotopes have increased several folds. A number of radioisotopes of different physical half-life, energy of the particle or gamma emission, specific activity and chemistry are now regularly produced both at commercial centers as well as at selected nuclear science research institutes utilizing reactors and cyclotrons to meet the ever growing need

Methodology to administer therapeutic dose of I-131

International Nuclear Information System (INIS)

Basteris M, J.; Gomez D, R.

2007-01-01

The present work suggests the use of measures guided to eliminate the resulting chronic sialoadenitis of the treatment of the thyroid cancer with Iodine-131, as well as the use of citric fruits to stimulate the salivation, the post-dose administration of liquids to accelerate the gastric emptying avoiding the secondary effects as the vomit is included. (Author)

Radioisotope identification method for poorly resolved gamma-ray spectrum of nuclear security concern

Energy Technology Data Exchange (ETDEWEB)

Ninh, Giang Nguyen; Phongphaeth, Pengvanich, E-mail: phongphaeth.p@chula.ac.th; Nares, Chankow [Nuclear Engineering Department, Faculty of Engineering, Chulalongkorn University, 254 Phayathai Road, Pathumwan, Bangkok 10330 (Thailand); Hao, Quang Nguyen [Vietnam Atomic Energy Institute, Ministry of Science and Technology, Hanoi (Viet Nam)

2016-01-22

Gamma-ray signal can be used as a fingerprint for radioisotope identification. In the context of radioactive and nuclear materials security at the border control point, the detection task can present a significant challenge due to various constraints such as the limited measurement time, the shielding conditions, and the noise interference. This study proposes a novel method to identify the signal of one or several radioisotopes from a poorly resolved gamma-ray spectrum. In this method, the noise component in the raw spectrum is reduced by the wavelet decomposition approach, and the removal of the continuum background is performed using the baseline determination algorithm. Finally, the identification of radioisotope is completed using the matrix linear regression method. The proposed method has been verified by experiments using the poorly resolved gamma-ray signals from various scenarios including single source, mixing of natural uranium with five of the most common industrial radioactive sources (57Co, 60Co, 133Ba, 137Cs, and 241Am). The preliminary results show that the proposed algorithm is comparable with the commercial method.

Radioisotope identification method for poorly resolved gamma-ray spectrum of nuclear security concern

International Nuclear Information System (INIS)

Ninh, Giang Nguyen; Phongphaeth, Pengvanich; Nares, Chankow; Hao, Quang Nguyen

2016-01-01

Gamma-ray signal can be used as a fingerprint for radioisotope identification. In the context of radioactive and nuclear materials security at the border control point, the detection task can present a significant challenge due to various constraints such as the limited measurement time, the shielding conditions, and the noise interference. This study proposes a novel method to identify the signal of one or several radioisotopes from a poorly resolved gamma-ray spectrum. In this method, the noise component in the raw spectrum is reduced by the wavelet decomposition approach, and the removal of the continuum background is performed using the baseline determination algorithm. Finally, the identification of radioisotope is completed using the matrix linear regression method. The proposed method has been verified by experiments using the poorly resolved gamma-ray signals from various scenarios including single source, mixing of natural uranium with five of the most common industrial radioactive sources (57Co, 60Co, 133Ba, 137Cs, and 241Am). The preliminary results show that the proposed algorithm is comparable with the commercial method

Exposure of employees engaged on the production and quality control of radiopharmaceuticals labelled with Tc-99m and I-131

International Nuclear Information System (INIS)

Trtic, T.; Jovanovic, M.; Vranjes, S.; Vucina, J.; Vuksanovic, Lj.

1995-01-01

In this paper, the analysis is presented, of exposure control of employees in the Laboratory for radioisotopes, of the Vinca Institute of nuclear sciences, engaged in the production and quality control of the Tc-99m generator and radiopharmaceuticals labelled with Tc-99m and I-131. Effective doses equivalent (mSv) was measured by personal thermoluminescent dosimeter in the Laboratory for radiation and environmental protection each month. We calculated effective dose equivalents for each year in the period 1986-1990. Thirty one employees were analysed. They were separated into the groups both on the basis of radioisotope which they worked with and the kind of the professional work. The highest average effective doses equivalent were received in the group producing of Tc-99m generator (4-12.5 mSv) and in the group producing I-131 radiopharmaceuticals (3.55-13.73 mSv). (author)

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1986

International Nuclear Information System (INIS)

Lamar, D.A.

1988-01-01

Data were collected and compiled on radioisotopes produced and sold by Department of Energy (DOE) facilities, and on services rendered by DOE facilities. Compiled data were published and distributed in the document list of DOE Radioisotope Customers with Summary of Radioisotope Shipments, FY 1986, PNL-6361, October 1987. The DOE facilities that supplied information for the compilation were Argonne National Laboratory, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho National Engineering Laboratory, Los Alamos National Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratory, Savannah River Plant, and UNC Nuclear Industries, Inc. (Hanford). The data provided were reported in several different ways: (1) a list of radioisotopes and services provided by each facility; (2) a list of radioisotope customers, the supplying DOE facility, and the radioisotope or service provided to each customer; and (3) a list of the quantity and value of each radioisotope or service sold by each DOE facility. The sales information covered foreign customers, domestic private customers, and domestic DOE customers

Preliminary studies of Brazilian wood using different radioisotopic sources

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Gilberto; Silva, Leonardo Gondim de Andrade e, E-mail: gcarval@ipen.br, E-mail: ftgasilva@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

Due to availability and particular features, wood was one of the first materials used by mankind with a wide variety of applications. It can be used as raw material for paper and cellulose manufacturing; in industries such as chemical, naval, furniture, sports goods, toys, and musical instrument; in building construction and in the distribution of electric energy. Wood has been widely researched; therefore, wood researchers know that several aspects such as temperature, latitude, longitude, altitude, sunlight, soil, and rainfall index interfere with the growth of trees. This behavior explains why average physical-chemical properties are important when wood is studied. The majority of researchers consider density to be the most important wood property because of its straight relationship with the physical and mechanical properties of wood. There are three types of wood density: basic, apparent and green. The apparent density was used here at 12% of moisture content. In this study, four different types of wood were used: 'freijo', 'jequetiba', 'muiracatiara' and 'ipe'. For wood density determination by non-conventional method, Am-241, Ba-133 and Cs-137 radioisotopic sources; a NaI scintillation detector and a counter were used. The results demonstrated this technique to be quick and accurate. By considering the nuclear parameters obtained as half value layers and linear absorption coefficients, Cs-137 radioisotopic source demonstrated to be the best option to be used for inspection of the physical integrity of electric wooden poles and live trees for future works. (author)

A new integrative methodology for desertification studies based on magnetic and short-lived radioisotope measurements

International Nuclear Information System (INIS)

Oldfield, F.; Higgitt, S.R.; Maher, B.A.; Appleby, P.G.; Scoullos, M.

1986-01-01

The use of mineral magnetic measurements and short-lived radioisotope studies with 210 Pb and 137 Cs is discussed within the ecosystem watershed conceptual framework. Used in conjunction with geomorphological, sedimentological, palaeoecological and geochemical techniques, these methods can form the core of an integrated multidisciplinary study of desertification and erosion processes on all relevant temporal and spatial scales. 30 refs.; 4 figs

A phase 1 study of 131I-CLR1404 in patients with relapsed or refractory advanced solid tumors: dosimetry, biodistribution, pharmacokinetics, and safety.

Directory of Open Access Journals (Sweden)

Joseph J Grudzinski

Full Text Available (131I-CLR1404 is a small molecule that combines a tumor-targeting moiety with a therapeutic radioisotope. The primary aim of this phase 1 study was to determine the administered radioactivity expected to deliver 400 mSv to the bone marrow. The secondary aims were to determine the pharmacokinetic (PK and safety profiles of (131I-CLR1404.Eight subjects with refractory or relapsed advanced solid tumors were treated with a single injection of 370 MBq of (131I-CLR1404. Whole body planar nuclear medicine scans were performed at 15-35 minutes, 4-6, 18-24, 48, 72, 144 hours, and 14 days post injection. Optional single photon emission computed tomography imaging was performed on two patients 6 days post injection. Clinical laboratory parameters were evaluated in blood and urine. Plasma PK was evaluated on (127I-CLR1404 mass measurements. To evaluate renal clearance of (131I-CLR1404, urine was collected for 14 days post injection. Absorbed dose estimates for target organs were determined using the RADAR method with OLINDA/EXM software.Single administrations of 370 MBq of (131I-CLR1404 were well tolerated by all subjects. No severe adverse events were reported and no adverse event was dose-limiting. Plasma (127I-CLR1404 concentrations declined in a bi-exponential manner with a mean t½ value of 822 hours. Mean Cmax and AUC(0-t values were 72.2 ng/mL and 15753 ng • hr/mL, respectively. An administered activity of approximately 740 MBq is predicted to deliver 400 mSv to marrow.Preliminary data suggest that (131I-CLR1404 is well tolerated and may have unique potential as an anti-cancer agent.ClinicalTrials.gov NCT00925275.

Nuclear data for production of therapeutic radionuclides. Summary report of second research coordination meeting

International Nuclear Information System (INIS)

Sublet, J.-Ch.; Capote Noy, R.

2004-11-01

A summary is given of the Second Research Coordination Meeting on Nuclear Data for Production of Therapeutic Radionuclides. The new library of evaluated cross section will cover the reactor and/or accelerator production of therapeutic radionuclides to appropriate specific activities and purity along with the relevant decay data. There are a significant number of radioisotopes in use or being proposed for therapeutic applications. As a consequence of the work undertaken during the course of this CRP, the resulting completeness and accuracy of the nuclear data for the production of these nuclides to appropriate specific activities and purity along with the re-definition of their decay data should be adequate for safe and efficient medical applications. The radioisotopes to be considered in the CRP were divided into two categories: Established Radioisotopes (therapeutic radioisotopes that have established clinical uses) and Emerging Radioisotopes (less-commonly used but potentially interesting radioisotopes for which medical applications have been demonstrated). Experimental data compilations and selection and preliminary evaluations for each of the reactions were extensively discussed during the meeting. The recommendations for both established and emerging radionuclides, and validation/testing of the cross section library are summarized. Technical discussions and the resulting work plan of the Coordinated Research Programme are summarized for every reaction path to be evaluated, along with actions and deadlines. Participants' contributions to the RCM are also attached. (author)

Iodine-131 in breast milk following therapy for thyroid carcinoma

International Nuclear Information System (INIS)

Robinson, P.S.; Barker, P.; Campbell, A.

1994-01-01

This study evaluates breast milk secretion of 131 I following therapeutic adminstration of 4000 MBq of 131 I-iodide during lactation. Breast milk 131 I activity concentration was measured over a 32-day period. Dosimetry calculations were undertaken to estimate the period for discontinuation of breast feeding and the equivalent dose to the breasts. To achieve an infant effective dose 131 I-iodide adminstration is not undertaken during lactation and that breast feeding is discontinued several days prior to administration. 26 refs., 2 figs., 2 tabs

Modelling the cancer growth process by Stochastic Differential Equations with the effect of Chondroitin Sulfate (CS) as anticancer therapeutics

Science.gov (United States)

Syahidatul Ayuni Mazlan, Mazma; Rosli, Norhayati; Jauhari Arief Ichwan, Solachuddin; Suhaity Azmi, Nina

2017-09-01

A stochastic model is introduced to describe the growth of cancer affected by anti-cancer therapeutics of Chondroitin Sulfate (CS). The parameters values of the stochastic model are estimated via maximum likelihood function. The numerical method of Euler-Maruyama will be employed to solve the model numerically. The efficiency of the stochastic model is measured by comparing the simulated result with the experimental data.

Development of departmental standard for traceability of measured activity for 131I therapy capsules used in nuclear medicine

International Nuclear Information System (INIS)

Ravichandran, Ramamoorthy; Binukumar, J.P.

2011-01-01

International Basic Safety Standards (International Atomic Energy Agency, IAEA) provide guidance levels for diagnostic procedures in nuclear medicine indicating the maximum usual activity for various diagnostic tests in terms of activities of injected radioactive formulations. An accuracy of ± 10% in the activities of administered radio-pharmaceuticals is being recommended, for expected outcome in diagnostic and therapeutic nuclear medicine procedures. It is recommended that the long-term stability of isotope calibrators used in nuclear medicine is to be checked periodically for their performance using a long-lived check source, such as 137 Cs, of suitable activity. In view of the un-availability of such a radioactive source, we tried to develop methods to maintain traceability of these instruments, for certifying measured activities for human use. Two re-entrant chambers ((HDR 1000 and Selectron Source Dosimetry System (SSDS)) with 125 I and 192 Ir calibration factors in the Department of Radiotherapy were used to measure Iodine-131 ( 131 I) therapy capsules to establish traceability to Mark V isotope calibrator of the Department of Nuclear Medicine. Special nylon jigs were fabricated to keep 131 I capsule holder in position. Measured activities in all the chambers showed good agreement. The accuracy of SSDS chamber in measuring 192 Ir activities in the last 5 years was within 0.5%, validating its role as departmental standard for measuring activity. The above method is adopted because mean energies of 131 I and 192 Ir are comparable. (author)

Radioisotopes preparation with GA Siwabessy for application in health/medical

International Nuclear Information System (INIS)

Sunarhadijoso-Soenarjo

2003-01-01

The Center for Development of Radioisotopes and Radiopharmaceuticals (CDRR) has to improve its role and potency to comply domestic demand in radioisotope preparations. The radioisotopes are used as both primary radioisotopes and labeled compounds, especially for medical diagnosis and therapy as radiopharmaceutical preparations. The implementation of capability in production of radioisotopes and radiopharmaceuticals is fully affected by the readiness of operational function of supporting facilities in regard to maintain safety system, process and personnel as well. For those reasons, activities program has been carried out with the aims of : (a). To faithful capability in production of GA Siwabessy reactor based radioisotopes, labeled compounds and radiopharmaceutical kits, (b). To optimize normal operational function of supporting facilities and utilities, and (c). To perform invention and modification of heater and temperature control units on the air handling unit (AHU) system. Some kinds of radioactive products are dominant during the year of 2002, i.e. 153 SmCl 3 , Na 2 99 MoO 4 and Na 186 ReO 4 primary radioisotopes and 153 Sm-EDTMP labeled compound. The main utilization of the products is for research and development of processing technology and medical application as diagnostic or therapeutic agent. The operational function of supporting facilities and utilities was well performed meeting the requirement of the users. Some units of the systems partially showed degradation of working performance but it did not cause trouble in security and safety of the system, process and personnel. A heater device completed with control system has been installed as a modified part of AHU system and has been tested successfully. The operation of the heater device is significantly influential to the air temperature and humidity in working area. The required air condition, e.g. 22 - 25 o C of temperature and 40 - 50 % of humidity, can be complied on the blower motor

Multiscale Modeling of Radioisotope Transfers in Watersheds, Rivers, Reservoirs and Ponds of Fukushima Prefecture

Science.gov (United States)

Zheleznyak, M.; Kivva, S.; Nanba, K.; Wakiyama, Y.; Konoplev, A.; Onda, Y.; Gallego, E.; Papush, L.; Maderych, V.

2015-12-01

The highest densities of the radioisotopes in fallout from the Fukushima Daiichi NPP in March 2011 were measured at the north eastern part of Fukushima Prefecture. The post-accidental aquatic transfer of cesium -134/137 includes multiscale processes: wash-off from the watersheds in solute and with the eroded soil, long-range transport in the rivers, deposition and resuspension of contaminated sediments in reservoirs and floodplains. The models of EU decision support system RODOS are used for predicting dynamics of 137Cs in the Fukushima surface waters and for assessing efficiency of the remediation measures. The transfer of 137Cs through the watershed of Niida River was simulated by DHSVM -R model that includes the modified code of the distributed hydrological and sediment transport model DHSVM (Lettenmayer, Wigmosta et al.) and new module of radionuclide transport. DHSMV-R was tested by modelling the wash-off from the USLE experimental plots in Fukushima prefecture. The model helps to quantify the influence of the differentiators of Fukushima and Chernobyl watersheds, - intensity of extreme precipitation and steepness of watershed, on the much higher values of the ratio "particulated cesium /soluted cesium" in Fukushima rivers than in Chernobyl rivers. Two dimensional model COASTOX and three dimensional model THREETOX are used to simulate the fate of 137Cs in water and sediments of reservoirs in the Manogawa River, Otagawa River, Mizunashigawa River, which transport 137Cs from the heavy contaminated watersheds to the populated areas at the Pacific coast. The modeling of the extreme floods generated by typhoons shows the resuspension of the bottom sediments from the heavy contaminated areas in reservoirs at the mouths of inflowing rivers at the peaks of floods and then re-deposition of 137Cs downstream in the deeper areas. The forecasts of 137Cs dynamics in bottom sediments of the reservoirs were calculated for the set of the scenarios of the sequences of the high

Iodine-131 labelled octreotide: not an option for somatostatin receptor therapy

International Nuclear Information System (INIS)

Bakker, W.H.; Breeman, W.A.P.; Pluijm, M.E. van der; Jong, M. de; Visser, T.J.; Krenning, E.P.

1996-01-01

This study deals with the radioiodination of very small amounts of peptide on a therapeutic scale, the required purification procedures after radioiodination, and the influence of high beta fluxes from 131 I on a peptide during radioiodination and purification. Based on the regularly used therapeutic doses of 131 I in cancer treatment and out previous experience with [ 111 In-DTPA-D-Phe 1 ]-octreotide, it was assumed that a minimal effective therapeutic dose of 3.7 GBq 131 I has to be coupled to a maximum of ∼100 μg peptide, representing only a slight excess of peptide over 131 I. This contrasts with non-peptide radiopharmaceuticals in which high compound to radionuclide ratios are usually used. Labelling at low peptide to radionuclide ratios (low labelling yields) results in the formation of di-iodinated compounds, whereas at high peptide to radionuclide ratios mono-iodinated products of low specific activity are formed. Thus, after radioiodination the desired mono-iodinated peptide has to be separated form unreacted iodide, and from di-iodinated and unreacted peptide, as both compounds compete for the receptors. Possible radiolysis of the peptide during labelling and separation steps were investigated by irradiating 30 μg unlabelled peptide with 370 MBq 131 I in a small volume. The peptide composition of the incubation mixtures was investigated by high-performance liquid chromatography after irradiation for 30 min to 24 h. The results showed that the peptide was degraded with a half-life of less than 1 h. During the preparation of a real therapeutic dose (at much higher β-flux) the peptide will be degraded even faster during the various steps required. In conclusion, intact mono-iodinated 131 I-labelled somatostatin analogues for peptide receptor therapy will be difficult to obtain. (orig./VHE)

Microbiological quality control practices at Australian Radioisotopes

International Nuclear Information System (INIS)

Saunders, M.

1987-01-01

As a domestic manufacturer of therapeutic substances, Australian Radioisotopes (ARI) must adhere to guidelines set out by the Commonwealth Department of Health in the Code of Good Manufacturing Practices for Therapeutic Goods 1983 (GMP). The GMP gives guidelines for staff training, building requirements, sanitation, documentation and quality control practices. These guidelines form the basis for regular audits performed by officers of the National Biological Standards Laboratories. At Lucas Heights, ARI has combined the principles of the GMP with the overriding precautions introduced for environmental and staff safety and protection. Its policy is to maintain a high level of quality assurance for product identity, purity and sterility and apyrogenicity during all stages of product manufacture

A Survey on the Usage and Demand of Medical Radioisotope and Radiopharmaceuticals in Malaysia

International Nuclear Information System (INIS)

Muhammad Fakhrurazi Ahmad Fadzil; Siti Selina Abdul Hamid; Siti Najila Mohd Janib; Azahari Kasbollah; Syed Asraf Fahlawi Wafa

2015-01-01

Medical radioisotope is a small quantity of radioactive substance used in safe, cost effective, for the purpose of diagnostic and therapy of various diseases. In Malaysia, the emerging of new nuclear medicine centers or institutions in both government and private sectors rose abruptly for the past few years. Currently, there are no data available on the usage and demand of medical radioisotope or radiopharmaceuticals. Understanding the usage trending and demand of radiopharmaceuticals and medical radioisotope is essential when related to technology changes in order to meet the market size of these radiopharmaceuticals. Survey result found out that the highest demand and the highest usage among all radioisotopes are Technetium-99m and Radioiodine isotopes such as the Iodine-1331, Iodine131 MIBG, Iodine-123 and Iodine-123 MIBG. Currently, most of the medical isotopes and radiopharmaceuticals are currently imported. Technetium-99m is the backbone of nuclear medicine whereby more than 80 % of Nuclear Medicine services utilize this radioisotope. Technetium-99m supply chain is unstable globally and in coming future, two main reactors (Canada and Holland) that produces 60 % of world Molybdenum-99 will shut down the operation and supply of Molybdenum-99 will be disrupted. As for radioiodine services, currently, Iodine-123 can't be obtained in Malaysia and neighboring countries due to its short half-life, Iodine-123 is useful in diagnostic of thyroid related diseases. As for PET services, the highest demands are F-18 FDG and Gallium-68 Generator for the moment. However the survey data still did not include most of the PET centers in the Klang Valley, northern area (Penang) and the new upcoming PET center in Southern Region (Malacca and Johor). It is important for Malaysia to self-produced medical radioisotope and radiopharmaceuticals to meet the market and local demand of these medical isotopes. (author)

Experimental study on Kd of 137Cs at varying suspended load conditions

International Nuclear Information System (INIS)

Jaison, T.J.; Jain, Abhishek; Patra, A.K.; Ravi, P.M.; Tripathi, R.M.

2018-01-01

137 Cs is one of the radionuclide likely to be released through liquid effluents from a nuclear facility. It is soluble in water, but its mobility in aquatic environments is highly retarded by its strong interaction with suspended sediment. The 137 Cs + sorption by suspended load, especially in the subtropics and tropics are not fully understood. Besides, according to IAEA document in emergency situation 137 Cs and 131 I being marker radionuclides, are easier to identify and representative of all the other radionuclides present. Hence a laboratory study is carried out on sorption of 137 Cs with varying silt load, using the upstream lake water and sediments to estimate site specific distribution coefficient (K d )

The use of radioisotopes in medicine and medical research, Australia 1947-73

Energy Technology Data Exchange (ETDEWEB)

Korszniak, N

1994-12-01

On March 31, 1994, an article appeared in the Melbourne Age claiming that after the Second World War `hundreds of people were injected with radioactive materials in medical experiments that continued in Australian hospitals until the 1960s. Similar reports subsequently appeared in other newspapers and on the television and radio news. The archival records held at the Australian Radiation Laboratory (ARL) pertaining to the medical uses of radioisotopes during the period 1947-1973 have been examined to ascertain the nature of radioisotope use, and in the case of experimental procedures, any ethical considerations. The material examined indicates that the distribution and medical use of radioactive isotopes was stringently controlled by the Radio-isotope Standing Committee (established by the National Health and Medical Research Council (NHMRC) in 1947 to oversee this area) until its disbandment in 1973, when the responsibility for regulation of the use of radioactive isotopes for medical purposes in Australia passed to the Therapeutic Goods Administration. A database, showing details of over 500 radioisotope use in Australia between 1947-1973 is given in Appendix III . (author) refs., tabs.

The use of radioisotopes in medicine and medical research, Australia 1947-73

International Nuclear Information System (INIS)

Korszniak, N.

1994-12-01

On March 31, 1994, an article appeared in the Melbourne Age claiming that after the Second World War 'hundreds of people were injected with radioactive materials in medical experiments that continued in Australian hospitals until the 1960s. Similar reports subsequently appeared in other newspapers and on the television and radio news. The archival records held at the Australian Radiation Laboratory (ARL) pertaining to the medical uses of radioisotopes during the period 1947-1973 have been examined to ascertain the nature of radioisotope use, and in the case of experimental procedures, any ethical considerations. The material examined indicates that the distribution and medical use of radioactive isotopes was stringently controlled by the Radio-isotope Standing Committee (established by the National Health and Medical Research Council (NHMRC) in 1947 to oversee this area) until its disbandment in 1973, when the responsibility for regulation of the use of radioactive isotopes for medical purposes in Australia passed to the Therapeutic Goods Administration. A database, showing details of over 500 radioisotope use in Australia between 1947-1973 is given in Appendix III . (author)

Radioisotopes for diagnosis and treatment: recent trends and path forward

International Nuclear Information System (INIS)

Dash, Ashutosh

2016-01-01

Radioisotopes play a significant and indispensable role in studying and understanding biological processes, viewing internal biological structures and processes for diagnosis of abnormal conditions, and in cure and alleviation of sufferings of cancer patients. With the availability of large number of diagnostic agents, SPECT and PET are matured technologies and is the mainstay of functional diagnostic imaging. Treatment of cancer with radioisotopes provides effective cure and the palliation of intractable symptoms. In a country like India, where more than 70% patients present in advanced and inoperable stages, radiation therapy plays an important role. While PET has seen the maximum growth in the last 15 years, next phase of growth of nuclear medicine is expected to be in radionuclide therapy. The new imaging modalities that appeared on the market at this very beginning of the new century and the new molecules and therapeutic technologies associated to the radioactivity open a very encouraging window that fascinates experts from other medical disciplines, and more particularly the oncologists, the hematologists and the neurologists. Cancer treatment remains at the forefront of any new therapeutic modality

Peculiarities of the contamination with radionuclides of the cultured pasture grass of the Lithuanian SSR after the Chernobyl accident

International Nuclear Information System (INIS)

Nedvetskajte, T.N.; Filistovich, V.I.; Petrulis, R.A.; Dauskurdis, S.I.; Tamulenajte, O.P.; Chias, K.V.

1989-01-01

Data on the contamination of pastures in the Lithuanian SSR with 131 I after the Chernobyl accident are given on the basis of measuring the grass samples from the cultured pastures. The predominant radionculides on the grass in the north-eastern and central parts of Lithuanie were 1 31 I and 103 Ru, while in its western and southern parts the 141 Ce, 144 Ce, 134 Cs, 137 Cs and other radioisotopes as well as hot particles predominated. The value of the grass-milk transfer coefficient was specified. 2 refs.; 5 figs

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1984

International Nuclear Information System (INIS)

Baker, D.A.

1985-08-01

This edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, Department of Energy (DOE). This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfers - FY 1984

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1984

Energy Technology Data Exchange (ETDEWEB)

Baker, D.A.

1985-08-01

This edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research (ER-73), Office of Energy Research, Department of Energy (DOE). This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfers - FY 1984.

Iodobell in vivo kits for labelling with 123I or 131I

International Nuclear Information System (INIS)

Koernyei, J.; Horvath, M.; Pszota, A.; Lakatos, M.; Szirtes, L.

1988-01-01

Iodobell in vivo kits provide an easy and fast method for 'on the spot' radioiodination with 123 I (or 131 I). Until now three kits have been developed in the Institute of Isotopes Budapest, the heptadecanoic acid, the hippurate and the MIBG kits. From these, the heptadecanoic acid kit is being tested in humans in Hungary, the other two are under the registration procedure. The Iodobell in vivo kits may contribute to the application of 123 I radioisotope in Hungary. (orig.)

Historical sketch of the discovery, production, and application of radioisotopes

International Nuclear Information System (INIS)

Williams, C.

1975-01-01

The Joliot-Curies made the first artificial radioisotope ( 30 P) by bombarding aluminum with alpha particles. The development of the cyclotron and other high-energy particle accelerators in the early 1930's led to the production of numerous radioisotopes in measurable quantities. By the beginning of the 1950's, with the abundant neutron fluxes available at the U. S. Atomic Commission reactors, radioisotopes of many species really became abundant. Naturally occurring radioactive lead had been used very sparingly as tracers as far back as 1918 in determining chemical solubility and in 1923 in plant uptake from lead solutions. Now many new uses were developed and tested as tracers in medical diagnosis, agricultural, and industrial chemical and metallurigical processes. Many therapeutic applications were tested. The industrial labs developed thickness and level gauges for control of various manufacturing processes. Cobalt gamma-ray irradiators were developed for medical therapy and have also been used for sterilization of surgical instruments and materials, for food preservation, and for initiation of certain chemical reactions. The most significant development in the 1960's was the rapidly increasing role of private industry in taking over the development, production, sales, as well as research, into new methods of production and applications of radioisotopes

Radioisotope detection with accelerators

International Nuclear Information System (INIS)

Mast, T.S.; Muller, R.A.; Tans, P.P.

1979-12-01

High energy mass spectrometry is a new and very sensitive technique of measuring rare radioisotopes. This paper describes the techniques used to select and identify the individual radioisotope atoms in a sample and the status of the radioisotope measurements and their applications

Validation of 131I ecological transfer models and thyroid dose assessments using Chernobyl fallout data from the Plavsk district, Russia

Science.gov (United States)

Zvonova, I.; Krajewski, P.; Berkovsky, V.; Ammann, M.; Duffa, C.; Filistovic, V.; Homma, T.; Kanyar, B.; Nedveckaite, T.; Simon, S.L.; Vlasov, O.; Webbe-Wood, D.

2009-01-01

Within the project “Environmental Modelling for Radiation Safety” (EMRAS) organized by the IAEA in 2003 experimental data of 131I measurements following the Chernobyl accident in the Plavsk district of Tula region, Russia were used to validate the calculations of some radioecological transfer models. Nine models participated in the inter-comparison. Levels of 137Cs soil contamination in all the settlements and 131I/137Cs isotopic ratios in the depositions in some locations were used as the main input information. 370 measurements of 131I content in thyroid of townspeople and villagers, and 90 measurements of 131I concentration in milk were used for validation of the model predictions. A remarkable improvement in models performance comparing with previous inter-comparison exercise was demonstrated. Predictions of the various models were within a factor of three relative to the observations, discrepancies between the estimates of average doses to thyroid produced by most participant not exceeded a factor of ten. PMID:19783331

Experimental dosimetry and kinetics of radioactive tracers for human applications: example of therapeutic injection of Lipiodol labelled with Iodine 131

International Nuclear Information System (INIS)

Ahmed Mahidi, N.

1992-10-01

We have evaluated the radiation dose received by the liver and lungs for 10 patients with a hepatic carcinoma after surgical operation followed by a therapeutic dose of Lipiodol labelled with iodine 131. The cumulated activities have been obtained by using a calibrated gamma camera. Fixation and kinetics of the I 131 Lipiodol in normal and cancers livers have been measured with the determination of the effective and biological half-lives. The calculated doses are based on the MIRD method. Results confirm that Lipiodol fixation is important in the liver at J1 (about 74% of the injected activity). Its elimination is essentially urinary, pulmonary fixation remained low, the dose received by the healthy part of liver is acceptable. These values have been compared with those obtained by another method using a thermoluminescent dosimeter (LiF) installed on the skin over the liver. Comparison between results obtained by the 2 methods shows a good correlation

Adsorption of Cs-137 and U-238 in semi-arid soils

International Nuclear Information System (INIS)

Hernandez T, U. O.; Monroy G, F.; Anguiano A, J.; Fernandez R, E.

2013-10-01

Is of great importance to determine the adsorption properties of the soils where radioactive wastes are stored, fundamentally of the radioisotopes contained in these wastes, with the purpose of knowing like will be their behavior in the event of happening radionuclide migration toward the surrounding means. Therefore, in this work the adsorption properties of 137 Cs + and 238 UO 2 2+ in soils coming from the Storage Center of Radioactive Wastes are studied. Was studied the effect of the soil type and the particle size of the soil in the adsorption properties of Cs (I) and U (Vi). 13 soil samples and six different particle sizes were analyzed. The adsorption studies were carried out by the radiotracers technique in static way. The results indicate an important adsorption affinity toward the Cs-137 and a very vulnerable affinity for the 238 UO 2 2+ . (author)

Internal contamination in nurses attending patients, that received therapeutic amounts of radioiodine-131

International Nuclear Information System (INIS)

Termorshuizen, W.; Gerritsen, A.J.M.

1988-01-01

The most frequent and often very successful used unsealed source in Nuclear Medicine and Radiotherapy is the radioiodine-131 for the treatment of thyroid carcinoma and hyperthyroidism. Always there is a great concern about the health physics of radioiodine and possible internal contamination involved in high level 131-I thyroid therapy cases, in particular to the thyroid as target and limiting organ. This report deals with 131-I air concentrations and internal contamination in nurses attending these patients under two different conditions. During the past three years a change took place from the old building, where we had an unventilated two-bed nursing room, to a new building were we have rooms with forced ventilation and air-conditioning (refreshment five times per hour). From both external exposure caused by radioiodine treated patients and internal contamination due to ingestion and inhalation of 131-I, we calculated the dose-equivalent to the thyroid and the effective dose-equivalent to our health care personnel

p38- and MK2-dependent signalling promotes stress-induced centriolar satellite remodelling via 14-3-3-dependent sequestration of CEP131/AZI1

DEFF Research Database (Denmark)

Tollenaere, Maxim A X; Villumsen, Bine H; Blasius, Melanie

2015-01-01

Centriolar satellites (CS) are small granular structures that cluster in the vicinity of centrosomes. CS are highly susceptible to stress stimuli, triggering abrupt displacement of key CS factors. Here we discover a linear p38-MK2-14-3-3 signalling pathway that specifically targets CEP131 to trig...

In patients with well differentiated thyroid carcinoma, the blind administration for 131I for ablation or therapeutical purposes could be avoid

International Nuclear Information System (INIS)

Garcia del Rio, H.; Degrossi, Osvaldo J.; Alak, M. del C.; Balbuena, R.L.; Valest, S.; Copat, L.; Alvarez, L.

2004-01-01

Several physicians considering the possibility of stunning or under rhTSH stimulation, indicate the administration of high activities of 131 I with the uncertainty of the existence of normal or pathological thyroid tissue concentrating radioiodine. This procedure reach its maximum score in the so called 'shoot in the dark' (SD). Other groups of physicians and the medical physics, considering the increasing radio sanitary risk and the dubious results of the use of SD, are not in agree with this position. A third position is the utilization of 123 I, that remains out of possibilities for the majority of the nuclear medicine laboratories. In a effort to conciliate these mismatched positions we propose the following procedure utilizing 99m Tc as pertechnetate, as its radiation dose is negligible compared with dose of radioiodines. We study 2 groups of patients DTC, G-A, 6 patients, 5 female, 1 male, 39-56 years old; with indication of 131 I administration for follow up or therapeutic purposes, 2 with rhTSH stimulation and 4 withdrawing hormone therapy; G-B, 5 patients, 4 females 1 male, 32-92 years old, with indication of scintigraphy previous to 131 I ablation post surgery. In both groups, previous to radioiodine, the same day, 370 MBq of 99m Tc pertechnetate was administered iv and a whole body scan (WBS) and uptake (Up) of positive areas were carried out. Immediately radioiodine was administered, 148 MBq in G-A and 11.1 MBq in G-B and WBS and Up were performed at 48 and 24 hours respectively. In all patients serum figures of TSH, Tg and antibodies anti Tg were obtained. The images obtained with both radioactive tracer were similar in all cases, as well as the active areas with positive uptake values. The Up for both tracer in positive areas was different in agree with the differences in the mechanism of concentration and metabolic behavior. These preliminary results allow us to considered that 99m Tc Up and WBS could be used top determine the possibility of 131 I

I-131 attraction by thyroid during first hours following its oral administration

International Nuclear Information System (INIS)

Franquiz, J.M.; Cardenas, R.; Blanco, J.; Garcia, M.

1982-01-01

From radioisotopic investigations used to study thyroid function, that of I-131 attraction results to be one of the most known and used in medical practice. In the authors' laboratory measurement of I-131 activity upon the gland has been for long adopted at 24 hours after administration; however, current needs compel to look for an early time (within the first six hours) for measuring it. In the paper results of I-131 attraction by thyroid in a group with more than 200 patients at 2,4 and 24 hours following its administration are presented in order to assess a 24 hours attraction representativeness by an early attraction. Results demonstrate early attraction is representative of an attraction at 24 hours and with the same diagnostic usefulness. Normal and doubtful ranks for attraction in our medium are determined at 2 and 6 hours, being adopted as proceeding for those cases whose value should be found within doubtful rank, a measurement at 24 hours in order to determine functional condition of the gland. (author)

Present situation of the production and use of radioisotopes in France

International Nuclear Information System (INIS)

Fisher, Charlie

1974-01-01

As the sole large scale producer of radioisotopes in France, the Commissariat a l'Energie Atomique is keeping up pace with all developments in medical, biological and industrial areas. This production will reach the turnover close to 40 million F in 1973. About 65% of the products will go to medical market, 10% to biology and the remaining 25% to industry. As medical products, many radioisotopes are used for in-vivo diagnosis, while radioimmunology techniques are well known in in-vitro diagnosis. There has been very few noticeable development in therapeutics. Also there is steadily increasing demand for 14 C, 3 H and 13 C-labelled materials which are used to study metabolism of natural substances and drugs. The industrial utilization of radioisotopes in France is developed by CEA as well as several industrial companies. Trend must be analyzed for the different segments of the market which includes tracer utilization, instrumentation, large source technology such as sterilization of medical supplies, activation analysis and isotopic generators. (Wakatsuki, Y.)

The feature and distribution of 137Cs in the forest soil

International Nuclear Information System (INIS)

Narazaki, Yukinori

2002-01-01

The 137 Cs concentration in an undisturbed upper layer of naked land in Fukuoka Prefecture decreased exponentially from 1969 to 1999 with the apparent half-life of 7 years. The ratio of 137 Cs concentration in the lower layer of the soil to that in the upper layer was about 1/5. The concentration of 137 Cs, 40 K, and stable Cs and the soil profile consisting of loss on ignition, pH, and electric conductivity were determined in the 48 samples collected in the forests and the neighboring naked land from 1991 to 1998. The 137 Cs concentration in the forest soils ranged from 1 to 424 Bq/kg dry wt, 131 Bq/kg dry wt on average, although 137 Cs was hardly detected in the naked soil around the forest. There was no regional difference in the distribution of the 137 Cs concentration, and it varied with pH and electric conductivity in the soil. Further, it tended to be higher in the deciduous woodland than in the evergreen woodland. (author)

Production of medical radioisotopes in the ORNL High Flux Isotope Reactor (HFIR) for cancer treatment and arterial restenosis therapy after PTCA

International Nuclear Information System (INIS)

Knapp, F.F. Jr.; Beets, A.L.; Mirzadeh, S.; Alexander, C.W.; Hobbs, R.L.

1998-01-01

The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) represents an important resource for the production of a wide variety of medical radioisotopes. In addition to serving as a key production site for californium-252 and other transuranic elements, important examples of therapeutic radioisotopes which are currently routinely produced in the HFIR for distribution include dysprosium-166 (parent of holmium-166), rhenium-186, tin-117m and tungsten-188 (parent of rhenium-188). The nine hydraulic tube (HT) positions in the central high flux region permit the insertion and removal of targets at any time during the operating cycle and have traditionally represented a major site for production of medical radioisotopes. To increase the irradiation capabilities of the HFIR, special target holders have recently been designed and fabricated which will be installed in the six Peripheral Target Positions (PTP), which are also located in the high flux region. These positions are only accessible during reactor refueling and will be used for long-term irradiations, such as required for the production of tin-117m and tungsten-188. Each of the PTP tubes will be capable of housing a maximum of eight HT targets, thus increasing the total maximum number of HT targets from the current nine, to a total of 57. In this paper the therapeutic use of reactor-produced radioisotopes for bone pain palliation and vascular brachytherapy and the therapeutic medical radioisotope production capabilities of the ORNL HFIR are briefly discussed

Contamination of foodstuffs in Styria (Austria) by J-131 and Cs-137

International Nuclear Information System (INIS)

Ninaus, W.; Kahr, G.; Oswald, K.; Mueller, H.

1993-01-01

Cs-137 activities of various foodstuffs were measured from May to December 1986. Results from different sites are compared. In the particular case of blueberry there is a time series from 1985 to 1992

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1985

Energy Technology Data Exchange (ETDEWEB)

Baker, D.A.

1986-08-01

This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfer - FY 1985.

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1985

International Nuclear Information System (INIS)

Baker, D.A.

1986-08-01

This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1) isotope suppliers, facility contacts, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfer - FY 1985

An Optimized Design of Single-Channel Beta-Gamma Coincidence Phoswich Detector by Geant4 Monte Carlo Simulations

Directory of Open Access Journals (Sweden)

Weihua Zhang

2011-01-01

Full Text Available An optimized single-channel phoswich well detector design has been proposed and assessed in order to improve beta-gamma coincidence measurement sensitivity of xenon radioisotopes. This newly designed phoswich well detector consists of a plastic beta counting cell (BC404 embedded in a CsI(Tl crystal coupled to a photomultiplier tube. The BC404 is configured in a cylindrical pipe shape to minimise light collection deterioration. The CsI(Tl crystal consists of a rectangular part and a semicylindrical scintillation part as a light reflector to increase light gathering. Compared with a PhosWatch detector, the final optimized detector geometry showed 15% improvement in the energy resolution of a 131mXe 129.4 keV conversion electron peak. The predicted beta-gamma coincidence efficiencies of xenon radioisotopes have also been improved accordingly.

Comparison of whole-body 18F-FDG PET, 99mTc-MIBI SPET, and post-therapeutic 131I-Na scintigraphy in the detection of metastatic thyroid cancer

International Nuclear Information System (INIS)

Iwata, Masahiro; Kasagi, Kanji; Misaki, Takashi; Matsumoto, Keiichi; Nakamoto, Yuji; Iida, Yasuhiro; Ishimori, Takayoshi; Higashi, Tatsuya; Saga, Tsuneo; Konishi, Junji

2004-01-01

The usefulness of fluorine-18 fluorodeoxyglucose (FDG) positron emission tomography (PET) in differentiated thyroid cancer (DTC) has been demonstrated by many investigators, but in only a small number of studies have FDG-PET images been compared with those obtained using other non-iodine tumour-seeking radiopharmaceuticals. In most of the studies, planar imaging was performed for comparison using thallium-201 chloride or technetium-99m 2-methoxyisobutylisonitrile ( 99m Tc-MIBI). Furthermore, FDG-PET studies were not always performed in the hypothyroid state with increased levels of thyroid stimulating hormone (TSH), which are known to increase FDG uptake by DTC. The aim of this study was to compare the ability of FDG-PET to detect metastatic DTC with that of 99m Tc-MIBI whole-body single-photon emission tomography (SPET) and post-therapeutic iodine-131 scintigraphy, evaluated under TSH stimulation. Nineteen patients (8 men, 11 women; age range, 38-72 years, mean 60 years; 17 thyroidectomised and 2 inoperable patients following 131 I ablation of the remaining thyroid tissue; 16 papillary and 3 follicular carcinomas) with metastatic DTC underwent FDG-PET whole-body scan (WBS) and 99m Tc-MIBI SPET WBS at an interval of less than 1 week, followed by 131 I therapy. The SPET images were reconstructed using the maximum likelihood expectation maximisation (ML-EM) method. All patients were hypothyroid at the time of each scan. 131 I WBS was performed 3-5 days after oral administration of the therapeutic dose. A total of 32 lesions [10 lymph node (LN), 15 lung, 6 bone, 1 muscle] were diagnosed as metastases, as confirmed by histopathology and/or other imaging modalities (X-ray, US, CT, MRI, bone, 201 Tl and 131 I scans). FDG-PET, 99m Tc-MIBI SPET and post-therapeutic 131 I scintigraphy respectively revealed a total of 26 (81.3%), 20 (62.5%) and 22 (68.8%) lesions. These techniques respectively demonstrated nine (90.0%), eight (80.0%) and six (60.0%) LN metastases, and eleven

Preparation and evaluation of (131I)AgI particles: potential lungs perfusion imaging agent

International Nuclear Information System (INIS)

Chattopadhyay, Sankha; Das, Sujata Saha; Sinha, Samarendu; Sarkar, Bharat Ranjan; Ganguly, Shantanu; Chandra, Susmita; De, Kakali; Mishra, Mridula

2010-01-01

Since the discovery of iodine-131 (t 1/2 : 8 d) by Livingood and Seaborg (1938), this, and other radioisotopes of iodine, have found widespread use in nuclear medicine. The purpose of the present work was to formulate Ag 131 I particles and bio-evaluate the same. The Ag 131 I particles were prepared in acidic condition having 100% R.C. Purity. The biological evaluation of Ag 131 1 particles was made by injecting about 111-185 MBq of Ag 131 I particles preparations in female albino rabbits (2-2.5 kg weight) intravenously by femoral vein under urethane anesthesia. Imaging studies were performed under Gamma Camera. The entire amount of the Ag 131 I particles were found to deposit in the lungs and remained there almost unchanged for a certain period of time after the intervenous administration. The images showed excellent, uniform lung uptake with no interference from liver and spleen to the lower regions of right and left lobes. It showed a high accumulation in the rabbits lungs (>99%) and remained constant for at least for 20 min. It is also worthy to study with 123 I/ 124 I labelled AgI for lung imaging study. In conclusion, the synthetic radiopharmaceutical ( 131 I)-Silver iodide colloid can be prepared with a large particle size, in a simple and practical manner, and it has good potential for use as a perfusion imaging agent in lung scans

Production and utilization of radioisotopes

International Nuclear Information System (INIS)

Sekine, Toshiaki; Matsuoka, Hiromitsu

1999-01-01

A plan of developing radioisotopes with a high power proton accelerator of the Neutron Science Project is presented. The status of production and utilization of radioisotopes in Japan is briefly discussed. The radioisotopes to be produced for biomedical use are discussed together with the facility for production of those radioisotopes and for research with the products. (author)

Environmental dose in the Nuclear Medicine Department of the National Institute of Cancer

International Nuclear Information System (INIS)

Torres U, C. L.; Avila A, O. L.; Medina V, L. A.; Buenfil B, A. E.; Brandan S, M. E.; Trujillo Z, F. E.; Gamboa de Buen, I.

2009-01-01

The dosimeters TLD-100 and TLD-900 were used to know the levels of environmental dose in areas of the Nuclear Medicine Department of the National Institute of Cancer. The dosimeters calibration was carried out in the Metrology Department of the National Institute of Nuclear Research. The radioisotopes used in the studied areas are 131 I, 18 F, 67 Ga, 99m Tc, 111 In, 201 Tl and 137 Cs with gamma energies between 93 and 662 KeV. Dosimeters were placed during five months in the diagnostic, injection, waiting and PET rooms as well as hot room, waste room, enclosed corridors to patient rooms treated with 131 I and 137 Cs and witness dosimeters to know the bottom. The values found vary between 0.3 and 70 major times that those of bottom. The maximum doses were measured in the waste room and in the enclosed corridor to the patient rooms with cervical uterine cancer treated with 137 Cs. (Author)

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1986

International Nuclear Information System (INIS)

Lamar, D.A.

1987-10-01

This document describes radioisotope distribution from DOE facilities to private firms including foreign and other DOE facilities. The information is divided into five sections: (1)isotope suppliers, facility contact, and isotopes or services supplied; (2) customers, suppliers, and isotopes purchased; (3) isotopes purchased cross-referenced with customer numbers; (4) geographic locations of radioisotope customers; and (5) radioisotope sales and transfers for fiscal year 1986

The presence of I-131 in different environmental factors from N W of Romania after the Fukushima disaster

International Nuclear Information System (INIS)

Cosma, C.; Iurian, A.R.; Nita, D.C.; Begy, R.; Cindea, C.

2011-01-01

The earthquake that hit Japan in March 11, 2011, entailed a high radioactive release from Fukushima NPP during the next days. Based on the results of the reactors analysis, the Nuclear and Industrial Safety Agency from Japan (NISA) estimated that a total amount of 1.3x10 17 Bq 131 I and 6.1x10 15 Bq 137 Cs have been released into the atmosphere. The aim of this study is to quantify the Fukushima radioactivity contamination in Cluj county and surrounding areas of Transylvania region. The concentration of the fission products has been analyzed in rainwater, milk, vegetation, eggs and pollen during the period 28th of March, 2011 - 19th of April, 2011. The measurements have been carried out by means of gamma-spectroscopy, using two ORTEC spectrometers with HpGE detectors with 34.2% and 30% relative efficiency, respectively . The 364.5 keV gamma line was analysed to obtain the 131 I concentrations and Maestro software has been used for the automatic spectrum evaluation. The 134 Cs and 137 Cs nuclides were also analysed as based on the gamma line from 604.7 keV and 661 keV, respectively. Some measurements were also performed for aerosol iodine collected on paper filters. The 131 I was the first radionuclide detected in rainwater from Cluj-Napoca, in 28th of March 2011. In April 5, 2011, the sheep milk registered a maximum activity of 9.22 ± 0.95 Bq/l in Cluj area. It seems that the maximum level of radioiodine concentration in the N W region of Romania has been reached at around 4th of April, 2011. The results obtained for rainwater at the beginning of April are in accordance with the measurements carried out in Pitesti area for radioiodine in air and wet depositions. The 134 Cs has been found only in rainwater at the beginning of March. The values recorded for 137 Cs in rainwater were close to the detection limit of the spectrometer, being subject of uncertainty due to the suspension in atmosphere of this artificial radionuclide also from Chernobyl accident release

Limulus amebocyte lysate technique (LAL) for bacterial endotoxin control in radiodiagnosis agents (kits) and radioisotopes

International Nuclear Information System (INIS)

Morote, M.; Robles, A.; Ramos, B.; Otero, M.

1997-01-01

A procedure based on a fast technique of LAL individual kits has been devised to control bacterial endotoxins in radiodiagnosis agents (RDA): HEMTEC, DEIDA, PPI, AMD, GHCa, RENTEC, DMSA, MAA, TSC, HERTEC, DTPA, BRATEC and EDTMP as well as in radioisotopes I-131 and Tc99m. The procedures begins with the determination of the following values, injection volume (IV), endotoxin limits (EL), maximum valid dilution (MVD), total mass (TM), reconstitution volume (RV), concentration (mg/ml), and final dilution (FD). Subsequently, a procedure is carried out to conduct an 'in vitro' control of the radiodiagnosis agents and radioisotopes with LAL individual kits; the procedures includes: reconstitution of the sample to be controlled, dilution, inoculation of the diluted sample in LAL tubes and incubation at 37 o C for an hour. Finally, results are interpreted through the observation of gel formation or not in LAL tubes

ALARA implementation in 131I therapeutic capsule production facility

International Nuclear Information System (INIS)

Kumawat, Lalit; Swaminathan, N.; Sudheer, T.S.; Sachdev, S.S.; Arora, S.S.; Vairalkar, K.G.

2005-01-01

Sodium iodide 131 I solution had been invariably administered to patients for both diagnosis and therapy of thyrotoxicosis. The undue exposure to non-target organs has been over come by introducing NaI ( 131 I) in a gelatin capsule. BRIT has set up experimental facility for the preparation and the production volume has augmented into four fold due to increase in demand and the same facility is being used to cater the need. However, the adequately shielded facility (fume hood) used for (manual) dispensing activity in capsules, capsules and product vial capping, transfer of the vials into lead pots and activity measurement of each vial has resulted in significant increase in the personnel exposure. The sources had been identified and efforts were made to reduce the exposure in these operations. An annular shield was introduced around the dispenser, resulted in the reduction of radiation field at wrist level by a factor of three. Introduction of shielded automated dispenser and usage of longer tools for transfer and capping of vials has effected in two times reduction of collective wrist dose. Currently, the relocated capping station two meters away from the source certainly will bring down further exposure. (author)

Current status of radio-isotopes utilization

Energy Technology Data Exchange (ETDEWEB)

Singh, M [Banaras Hindu Univ. (India)

1974-08-01

Utilization of radioisotopes were reviewed briefly in a categorized manner. In plant biochemistry, long lived radioactive carbon ,/sup 14/C, was applied to clarify such metabolic processes as photosynthesis, respiration and protein synthesis, etc., while radioactive oxygen ,/sup 18/O, was used to study the O/sub 2/ generation mechanism. Radioactive phosphorus ,/sup 32/P, was used to detect the amount, grain size of phosphatic fertilizer as well as the time and depth for better utilization. Radioactive sulphur ,/sup 35/S, and nitrogen ,/sup 15/N, could be of use in studies of protein metabolism in plants. Radioactive tracers of other minerals such as N, P, K, Ca, Mg, Zn, Mo, B, and Co were also used to detect their specific role in plants. Use of radioactive isotopes in protein synthesis and transfer of genetic information was described. Radioactive iodine ,/sup 131/I, binding capacity of milk proteins, and radio trace studies in the iodine turn over in the use of radioactive iodine were summarized.

Transmutation effects on long-term Cs retention in phyllosilicate minerals from first principles.

Science.gov (United States)

Sassi, Michel; Okumura, Masahiko; Machida, Masahiko; Rosso, Kevin M

2017-10-11

The accidental release and incorporation of radiocesium into soil minerals represents a massive environmental, technical and social challenge. Accurately forecasting the evolving distribution and fate of long- and medium-lived isotopes such as 137 Cs and 134 Cs over decadal time scales is essential. The cesium cation has long been modeled as a strongly and selectively sorbed species into clay mineral interlayers; however, because of the time scales involved by the radioisotopes half-lives, the effects of radioactive decay on Cs retention have been unknown. We report density functional theory (DFT) simulations of transmutation effects of radiocesium on long-term Cs retention in phlogopite. The calculations show that the progressive appearance of daughter product Ba 2+ is accompanied by a proportional increase in thermodynamic driving force to preferentially discharge remaining Cs, both radioactive and stable, back into aqueous solution. Based on thermodynamic analysis, the findings indicate that radiocesium transmutation provides a mean to weaken the binding of Cs in phyllosilicate minerals, therefore potentially involving a premature re-release of Cs back into the environment. In the case where radiogenic Ba 2+ ions accumulate in the mineral, collateral effects would ultimately be an increase in the overall interlayer binding energy and a lower resorption capacity.

Applications of radioisotopes in medicine

International Nuclear Information System (INIS)

Sivaprasad, N.

2012-01-01

The application of radioisotopes in medicine is many folds. They can be classified into two main groups. (a) The radioisotope tagged labeled compounds suitable for safe administration in the body for diagnosis of various diseases of vital organs such as brain, kidney, thyroid etc and for treatment known as radiotherapy (b) The sealed source of radioisotopes for utilizing the radiation emitted from the radioisotope for treatment, particularly for radiation therapy of cancer. The former application of radioisotope in the field of medicine has led to the formation of special branch of medicine termed Nuclear Medicine - the branch of medicine deals with the use of radioisotope in the from of radiopharmaceuticals for investigation, diagnosis and treatment of diseases. Radioisotopes in the form of radiolabelled compound and bio-chemicals that are pharmaceutically and radiologically safe for administration in the body for diagnosis and treatment are called radiopharmaceuticals. The radiopharmaceuticals are the results of world-wide effort to bring nuclear energy in a tangible form for diagnosis and treatment. Radioisotopes as radiopharmaceuticals thus constitute one of the key requirements for nuclear medicine investigation and radiotherapy. In the case of sealed radioisotope source the radiation emitted by the radioactive source is utilized for the treatment and this mode of treatment is called radiation therapy where no radioactive substance is administrated into the body. This does not form the part of nuclear medicine

Evaluation of biological analysis program for iodine 131; Avaliacao do programa de bioanalise para Iodo-131

Energy Technology Data Exchange (ETDEWEB)

Gaburo, J.C.; Todo, A.S.; Potiens Junior, A.; Oliveira, E.M.; Sordi, G.M.A.A. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

1997-12-31

A program for the occupational control of internal contamination for the Radioisotopes Division workers of the IPEN-CNEN/SP has been performed by in vitro and in vivo bioassay techniques, every two weeks. From the assessment of the monitoring program, two groups of workers were identified in accordance with their activities and handling frequency {sup 131} I. The groups A and B are exposed five and three days respectively every week. In this program, urinalysis methods, thyroid and whole body measurements have been evaluated over the year. The sampling scheme, performed every two week, was altered for weekly, in order to minimize the interpretation errors and to get a better estimative of the intake. This study also provides and evaluation of the cost for the weekly urinalysis sampling method. (author) 6 refs., 1 fig.; e-mail: janetegc at net.ipen.br

Radionuclide study of thyroid function in pediatrics, using sup(99m)Tc, 123I or 131I: 150 case-reports

International Nuclear Information System (INIS)

Guillet, J.; Basse-Cathalinat, B.; Soubiran, G.; Blanquet, P.; Guillet, G.

1981-01-01

THe best radioisotope for in vivo thyroid investigations is the one which provides the highest quality scintigrams with the least radiation exposure. The choice of 131 I, 123 I or sup(99m)Tc in 150 children is discussed. Cases included 25 dysgenesis, 4 goiters with hypothyroidism, 56 goiters without thyroid dysfunction, 3 thyroiditis, and 11 cold nodules. When thyroid scanning is performed with 131 I, the gland's radiation exposure is high. 123 I is preferable since a fairly high activity can be obtained without delivering an excessive radiation dose. (approximately 2 rad to the thyroid for 50 microCi/m 2 ). sup(99m)Tc which is readily available is not a true iodine analog. It does not give a true picture of iodine metabolism. 123 I was generally used in cases of hypothyroidism, goiter (whenever a defect in thyroid hormone synthesis was suspected) and hyperthyroidism. sup(99m)Tc was generally used in other cases. The low radiation doses delivered by these radioisotopes allows study of thyroid function in the neonate [fr

Investigation of therapeutic efficiency of phenytoin (PHT) labeled with radioactive 131I in the cancer cell lines

International Nuclear Information System (INIS)

Cansu Uzaras; Ugur Avcibasi; Hasan Demiroglu; Emin Ilker Medine; Ayfer Yurt KiIcar; Fazilet Zuemruet Biber Mueftueler; Perihan Uenak

2016-01-01

The aim of this study is to determine the incorporations of PHT radiolabeled with 131 I ( 131 I-PHT) on U-87 MG, Daoy and A549 cancerous cell lines. For this, cold and radio-labeling studies were carried out. The radiolabeling yield of 131 I-PHT was obtained about 95 %. Subsequently, cell culture studies were carried out and radio-labeling yields of 131 I, 131 I-PHT on U-87 MG, Daoy and A549 cancerous cells were investigated. Cell culture studies demonstrated that the incorporation values of 131 IPHT on the three cell lines decreased with increasing radioactivity. Consequently, 131 I-PHT may be a good radiopharmaceutical for targeting radionuclide therapy of Central Nervous System Tumors. (author)

Methodology to administer therapeutic dose of I-131; Metodologia para administrar dosis terapeutica de I-131

Energy Technology Data Exchange (ETDEWEB)

Basteris M, J.; Gomez D, R. [Universidad Autonoma de Yucatan, Facultad de Medicina, Merida, Yucatan (Mexico)

2007-07-01

The present work suggests the use of measures guided to eliminate the resulting chronic sialoadenitis of the treatment of the thyroid cancer with Iodine-131, as well as the use of citric fruits to stimulate the salivation, the post-dose administration of liquids to accelerate the gastric emptying avoiding the secondary effects as the vomit is included. (Author)

Internal Contamination by 131I in nuclear medicine department

International Nuclear Information System (INIS)

Chahed, N.; Mtimet, S.; Hammami, H.; Mhiri, A.

1998-01-01

Therapeutic applications in nuclear medicine use high activities of 131 I in sodium iodine liquid from which is volatile at ambient temperature. Besides external exposure there is, for the nuclear medicine personnel, an internal exposure risk induced by 131 iodine inhalation. So we tried to assess this risk among the personnel in a nuclear medicine department. We used direct method for measuring 131 radioactivity in vivo by external counting. Gamma ray detector with a Nal ( TI ) probe positioned near the thyroid gland allows investigation of 131 radioactivity. We realised 34 measurements among the personnel, two times at an interval of one month. The results indicate that an 131 iodine internal contamination is found. Estimated thyroid activities were ranging from 35 to 132 Bq. The highest activities has been found in the thyroid of the technicians involved in the administration of 131 iodine therapy. Therefore this values are lower than norms. This study must lead to the implementation control of the 131 iodine internal contamination in order to optimise the personnel protection in nuclear medicine departments (author)

Radioisotopes production for applications on the health; Produccion de radioisotopos para aplicaciones en la salud

Energy Technology Data Exchange (ETDEWEB)

Monroy G, F.; Alanis M, J., E-mail: fabiola.monroy@inin.gob.m [ININ, Departamento de Materiales Radiactivos, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2010-07-01

In the Radioactive Materials Department of the Instituto Nacional de Investigaciones Nucleares (ININ) processes have been studied and developed for the radioisotopes production of interest in the medicine, research, industry and agriculture. In particular five new processes have been developed in the last 10 years by the group of the Radioactive Materials Research Laboratory to produce: {sup 99}Mo/{sup 99m}Tc and {sup 188}W/{sup 188}Re generators, the radio lanthanides: {sup 151}Pm, {sup 147}Pm, {sup 161}Tb, {sup 166}Ho, {sup 177}Lu, {sup 131}I and the {sup 32}P. All these radioisotopes are artificial and they can be produced in nuclear reactors and some of them in particle accelerators. The radioisotope generators are of particular interest, as those of {sup 99}Mo/{sup 99m}Tc and {sup 188}W/{sup 188}Re presented in this work, because they are systems that allow to produce an artificial radioisotope of interest continually, in these cases the {sup 99m}Tc and the {sup 188}Re, without the necessity of having a nuclear reactor or an particle accelerator. They are compact systems armored and sure perfectly of manipulating that, once the radioactive material has decayed, they do not present radiological risk some for the environment and the population. These systems are therefore of supreme utility in places where it is not had nuclear reactors or with a continuous radioisotope supply, due to their time of decaying, for its cost or for logistical problems in their supply, like it is the case of many hospital centers, of research or industries in our country. (Author)

Maps of surface activity of 137Cs of Slovakia on scale 1:200 000

International Nuclear Information System (INIS)

Gluch, A.

2005-05-01

The present set of maps (13 maps) arose from the geological project 'Re-ambulation of 137 Cs radioactivity map of Slovakia at scales 1:200 000 and 1:500 000' in phase of indicative geological survey of environmental factors. Maps document the state of contamination of the territory of Slovakia by one of the radioisotopes cesium-137 at the reference date 01.01.2005. In solving of geological tasks were used all available relevant data on measurements of 137 Cs activity from the whole territory of the Slovak Republic for the period from 1990 to 2003 from results of air and ground gamma spectrometric measurements. (authors)

Recent progress in development of radioisotope production

Energy Technology Data Exchange (ETDEWEB)

Yoon, Byung Mok [HANARO Center, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1998-10-01

The Korea multipurpose research reactor, HANARO(Hi-flux Advanced Neutron Application Reactor) is designed and constructed to obtain high density neutron flux (max. 5x10{sup 14} n/cm{sup 2}{center_dot}sec) with relatively low thermal output (30 MW) in order to utilize for various studies such as fuel and material test, radioisotope production, neutron activation analysis, neutron beam experiment, neutron transmutation doping, etc. HANARO has 32 vertical channels (3 in-core, 4 out-core, 25 reflector) and 7 horizontal channels. KAERI has constructed 4 concrete hot cells for production of Co-60, Ir-192, etc. and 6 lead hot cells for production of medical RIs(I-131, Mo-99, etc.). Other 11 lead hot cells will be completed by Feb. 1998 for production of Sm-153, Dy-165, Ho-166, etc. Clean room facilities were installed for production of radiopharmaceuticals. (author)

Radioisotope battery for particular application

International Nuclear Information System (INIS)

Shen Tianjian; Liang Daihua; Cai Jianhua; Dai Zhimin; Xia Huihao; Wang Jianhua; Sun Sen; Yu Guojun; Wang Xiao; Wang Dongxing; Liu Xin

2010-01-01

Radioisotope battery, as a new type of power source, was developed in 1960s. It is advantageous in terms of long working life, high reliability, flexibility to rugged environment, maintenance free, and high capacity rate, hence its unique applications in space, isolated terrestrial or ocean spots, deep waters, and medicine. In this paper, we analysz the primary performances and classification of radioisotope thermoelectric generator, as well as characteristic, basic principle,and structure of radioisotope thermoelectric generator (RTG), which is the most popular in application of radioisotope battery in space, undersea, terrestrial and medicine. A prospect for development and application of radioisotope battery in the 21 st century is given, too. (authors)

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1979

International Nuclear Information System (INIS)

Burlison, J.S.

1980-06-01

The fifteenth edition of the radioisotope customer list was prepared at the request of the Division of Financial Services, Office of the Assistant Secretary for Environment, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboratory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Rocky Flats Area Office; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: Isotope suppliers, facility, contracts and isotopes or services supplied; alphabetical list of customers, and isotopes purchased; alphabetical list of isotopes cross-referenced to customer numbers; geographical location of radioisotope customers; and radioisotope sales and transfers-FY 1979

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1981

International Nuclear Information System (INIS)

Burlison, J.S.

1982-09-01

The seventeenth edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research, Office of Energy Research, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory: Pacific Northwest Laboratory; Brookhaven National Laboratory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: (1) isotope suppliers, facility, contracts and isotopes or services supplied; (2) alphabetical list of customers, and isotopes purchased; (3) alphabetical list of isotopes cross-referenced to customer numbers; (4) geographical location of radioisotope customers; and (5) radioisotope sales and transfers-FY 1980

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1980

International Nuclear Information System (INIS)

Burlison, J.S.

1981-08-01

The sixteenth edition of the radioisotope customer list was prepared at the request of the Office of Health and Environmental Research, Office of energy Research, Department of Energy (DOE). This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Brookhaven National Laboraory; Hanford Engineering Development Laboratory; Idaho Operations Office; Los Alamos Scientific Laboratory; Mound Facility; Oak Ridge National Laboratory; Savannah River Laboratory; and UNC Nuclear Industries, Inc. The information is divided into five sections: (1) isotope suppliers, facility, contracts and isotopes or services supplied; (2) alphabetical list of customers, and isotopes purchased; (3) alphabetical list of isotopes cross-referenced to customer numbers; (4) geographical location of radioisotope customers; and (5) radioisotope sales and transfers-FY 1980

Iodine-131 Metaiodobenzylguanidine Therapy for Neuroblastoma: Reports So Far and Future Perspective

Directory of Open Access Journals (Sweden)

Daiki Kayano

2015-01-01

Full Text Available Neuroblastoma, which derives from neural crest, is the most common extracranial solid cancer in childhood. The tumors express the norepinephrine (NE transporters on their cell membrane and take in metaiodobenzylguanidine (MIBG via a NE transporter. Since iodine-131 (I-131 MIBG therapy was firstly reported, many trails of MIBG therapy in patients with neuroblastoma were performed. Though monotherapy with a low dose of I-131 MIBG could achieve high-probability pain reduction, the objective response was poor. In contrast, more than 12 mCi/kg I-131 MIBG administrations with or without hematopoietic cell transplantation (HCT obtain relatively good responses in patients with refractory or relapsed neuroblastoma. The combination therapy with I-131 MIBG and other modalities such as nonmyeloablative chemotherapy and myeloablative chemotherapy with HCT improved the therapeutic response in patients with refractory or relapsed neuroblastoma. In addition, I-131 MIBG therapy incorporated in the induction therapy was proved to be feasible in patients with newly diagnosed neuroblastoma. To expand more the use of MIBG therapy for neuroblastoma, further studies will be needed especially in the use at an earlier stage from diagnosis, in the use with other radionuclide formations of MIBG, and in combined use with other therapeutic agents.

Radioisotope measurement system

International Nuclear Information System (INIS)

Villanueva Ruibal, Jose

2007-01-01

A radioisotope measurement system installed at L.M.R. (Ezeiza Atomic Center of CNEA) allows the measurement of nuclear activity from a wide range of radioisotopes. It permits to characterize a broad range of radioisotopes at several activity levels. The measurement hardware as well as the driving software have been developed and constructed at the Dept. of Instrumentation and Control. The work outlines the system's conformation and its operating concept, describes design characteristics, construction and the error treatment, comments assay results and supplies use advices. Measuring tests carried out employing different radionuclides confirmed the system performing satisfactorily and with friendly operation. (author) [es

Aplicaciones clínicas del radioyodo 131 (I131 en las enfermedades del tiroides Clinical applications of radioiodine 131 (I131 in the thyroid diseases

Directory of Open Access Journals (Sweden)

Levi González Rivero

2012-12-01

Full Text Available El radioyodo 131 es un isótopo radioactivo que se emplea exitosamente en el diagnóstico y tratamiento de las enfermedades benignas y malignas del tiroides. Su propiedad de integrarse selectivamente al metabolismo del tiroides y emitir una señal, le permite describir el funcionamiento glandular mediante estudios de captación, y delimitar la morfología y localización de los tejidos que capten yodo, a través de la gammagrafía. Es además una radioterapia sencilla, segura y coste-efectiva, usada como primera línea terapéutica en el control del hipertiroidismo, cuya dosis y momento de aplicación debería individualizarse según la etiología y la clínica de cada paciente. El radioyodo 131 ofrece una alternativa eficaz para reducir el tamaño del bocio no tóxico; además, respalda el tratamiento quirúrgico del carcinoma diferenciado del tiroides, y destruye a dosis ablativa los restos tisulares y las lesiones metastásicas que puede identificar durante el seguimiento gammagráfico. El empleo de radioyodo 131 está sujeto al cumplimiento de regulaciones de protección contra la radioactividad.Radioiodine 131 is a radioactive isotope that is successfully used for the diagnosis and the treatment of benign and malignant thyroid diseases. Its quality of selectively integrating to the thyroid metabolism and emitting a signal allows it to describe the gland functioning through capture studies, and to delimit the morphology and location of the tissues that capture iodine by means of gammagraphy. It is also a simple, safe and cost-effective radiotherapy used as first-line therapeutics in the control of hyperthyroidism. The dose and right time of application should be individualized according to the etiology and the clinic of each patient. Radioiodine 131 offers an efficient alternative to reduce the size of non-toxic goiter in addition to supporting the surgical treatment of the differentiated thyroid carcinoma and destroying with ablative doses

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1983

International Nuclear Information System (INIS)

Baker, D.A.

1984-08-01

This document lists DOE's radioisotope production and distribution activities by its facilities at Argonne National Laboratory; Pacific Northwest Laboratory; Idaho Operations Office; Los Alamos National Laboratory; Oak Ridge National Laboratory; Savannah River Plant; and UNC Nuclear Industries, Inc. The information is divided into five sections: isotope suppliers, facility contacts, and isotopes or services supplied; lists of customers, suppliers and isotopes purchased; list of isotopes purchased cross-referenced to customer codes; geographic locations of radioisotope customers; and radioisotope sales and transfers - FY 1983

Samplings of airborne particulates for granulometric determinations following Chernobyl accident

International Nuclear Information System (INIS)

Tarroni, G.; Calamosca, M.; Zaiacomo, T. de; Gragnani, R.; Michetti, I.; Testa, L.

1988-01-01

Particle size distributions and concentrations of the radioactive aerosol that arose from the Chernobyl accident were determined in Bologna and Rome. The activity Median Aerodynamic Diameters (AMAD) of Ru-103, Te-132, Cs-134 and Cs-137, determined by means of impactors, were in the range 0.8 - 1.4 μm with Geometric Standard Deviations (Sg) in the range 1.6 - 3.7. Lower AMAD and higher Sg values were found for I-131 compared to those for the other radioisotopes. The gaseous fraction of I-131 was 60-70% of the total aerosuspended activity of this isotope. A comparison between direct measurement data concerning internal contamination on volunteers and values derived from air contamination data shows that in Bologna, during May 1986, almost all the contamination was due to inhalation. The data are unable to distinguish between different inhalation models

Research reactor production of radioisotopes for medical use

International Nuclear Information System (INIS)

Mani, R.S.

1985-01-01

More than 70% of all radioisotopes applied in medical diagnosis and research are currently produced in research reactors. Research reactors are also an important source of certain radioisotopes, such as 60 Co, 90 Y, 137 Cs and 198 Au, which are employed in teletherapy and brachytherapy. For regular medical applications, mainly 29 radionuclides produced in research reactors are used. These are now produced on an 'industrial scale' by many leading commercial manufacturers in industrialized countries as well as by national atomic energy establishments in developing countries. Five main neutron-induced reactions have been employed for the regular production of these radionuclides, namely: (n,γ), (n,p), (n,α), (n,γ) followed by decay, and (n, fission). In addition, the Szilard-Chalmers process has been used in low- and medium-flux research reactors to enrich the specific activity of a few radionuclides (mainly 51 Cr) produced by the (n,γ) reaction. Extensive work done over the last three decades has resulted in the development of reliable and economic large-scale production methods for most of these radioisotopes and in the establishment of rigorous specifications and purity criteria for their manifold applications in medicine. A useful spectrum of other radionuclides with suitable half-lives and low to medium toxicity can be produced in research reactors, with the requisite purity and specific activity and at a reasonable cost, to be used as tracers. Thanks to the systematic work done in recent years by many radiopharmaceutical scientists, the radionuclides of several elements, such as arsenic, selenium, rhenium, ruthenium, palladium, cadmium, tellurium, antimony, platinum, lead and the rare earth elements, which until recently were considered 'exotic' in the biomedical field, are now gaining attention. (author)

Long term simulation of {sup 137}Cs radioactivity in the regional ocean following the Fukushima Daiichi nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Tsumune, D.; Tsubono, T.; Misumi, K.; Yoshida, Y.; Hayami, H. [Central Research Institute of Electric Power Industry (Japan); Aoyama, M. [Meteorological Research Institute (Japan); Uematsu, M. [University of Tokyo (Japan); Maeda, Y. [CERES, Inc. (Japan)

2014-07-01

A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant following the earthquake and tsunami of 11 March 2011 resulted in the release of radioactive materials to the ocean by two major pathways, direct release from the accident site and atmospheric deposition. A regional-scale simulation of {sup 137}Cs activity in the ocean offshore of Fukushima was carried out, the sources of radioactivity being direct release, atmospheric deposition, and the inflow of {sup 137}Cs deposited on the ocean by atmospheric deposition outside the domain of the model for more than two years. Direct releases of {sup 131}I, {sup 134}Cs, and {sup 137}Cs were estimated for 1 year after the accident by comparing simulated results and measured activities. The estimated total amounts of directly released {sup 131}I, {sup 134}Cs, and {sup 137}Cs were 11.1±2.2 PBq, 3.5±0.7 PBq, and 3.6±0.7 PBq, respectively. The contributions of each source were estimated by analysis of {sup 131}I/{sup 137}Cs and {sup 134}Cs/{sup 137}Cs activity ratios and comparisons between simulated results and measured activities of {sup 137}Cs. Simulated {sup 137}Cs activities attributable to direct release were in good agreement with measured activities close to the accident site, a result that implies that the estimated direct release rate was reasonable, while simulated {sup 137}Cs activities attributable to atmospheric deposition were low compared to measured activities. The rate of atmospheric deposition onto the ocean was underestimated because of a lack of measurements of deposition onto the ocean when atmospheric deposition rates were being estimated. Measured {sup 137}Cs activities attributable to atmospheric deposition helped to improve the accuracy of simulated atmospheric deposition rates. Simulated {sup 137}Cs activities attributable to the inflow of {sup 137}Cs deposited onto the ocean outside the domain of the model were in good agreement with measured activities in the open ocean within the

Measurements of iodine uptake in thyroid after diagnostic administration of 131I

International Nuclear Information System (INIS)

Osko, J.; Pliszczynski, T.

2003-01-01

The measurements performed up to now, showed that the spectrometric measurements can be useful in selection of the patients who need special consideration during the 131 I diagnostics and treatment. The next step of the work will include the measurements of the real activity of 131 I in thyroid gland, after the therapeutic administration of radioiodine. A special collimator was designed for this purpose and the thyroid counter was calibrated using a phantom with inserts simulating different shapes of pathologically changed thyroid glands. It can be expected that the improvement of accuracy of the diagnostic measurements and better control of real activity of 131 I in thyroid gland after the therapeutic administration will contribute to the process of optimisation of radiation doses to the patients and medical personnel. (authors)

Manual on therapeutic uses of iodine-131. Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1992-01-01

This booklet contains information about procedures to protect hospital staff and visitors and families of patients treated with iodine 131 from exposure to radiation from I-131. It also includes a basic guide to the principles of the production of ionizing radiation and to methods of radiation protection and dosimetry

List of DOE radioisotope customers with summary of radioisotope shipments, FY 1982

International Nuclear Information System (INIS)

Richards, M.P.

1983-08-01

The radioisotope production and distribution activities by facilities at Argonne National Laboratory, Pacific Northwest Laboratory, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho Operations Office, Los Alamos Scientific Laboratory, Oak Ridge National Laboratory, Savannah River Laboratory, and UNC Nuclear Industries, Inc. are listed. The information is divided into five sections: isotope suppliers, facility, contacts, and isotopes or services supplied; alphabetical list of customers, and isotopes purchased; alphabetical list of isotopes cross-referenced to customs numbers; geographical location of radioisotope customers; and radioisotope sales and transfers-FY 1982

Medical radioisotopes in the environment - following the pathway from patient to river sediment

International Nuclear Information System (INIS)

Fischer, Helmut W.; Ulbrich, Susanne; Pittauerova, Daniela; Hettwig, Bernd

2009-01-01

Motivated by the detection of 131 I in river sediment in routine long-term surveillance samples, a systematic short-term study of the wastewater treatment chain was planned and conducted. Inflow, effluent and primary sludge were collected on a daily basis during two weeks at a regional wastewater treatment plant. Samples were investigated by gamma spectroscopy. Four medically used isotopes could be identified ( 131 I and 99m Tc regularly, 153 Sm and 123 I sporadically). The concentration levels coincide well with literature data for 131 I, and with our own long-term data for 131 I and 99m Tc for the same plant. Cosmogenic 7 Be activity in primary sludge correlated well with rainfall intensity. Surface sediment was sampled at low tide at both shores of the river, up- and downstream of the plant. 131 I was identified in all samples, with a sharp maximum (about 100 Bq kg -1 d.m.) at the discharge point of the plant and lower levels elsewhere, decreasing monotonically in downstream direction. 7 Be and 137 Cs showed the same behaviour, but no peak at the discharge point. Predictions from simple equilibrium models for the transport and sedimentation of 131 I show good agreement with the experimental data and suggest that the wastewater treatment plant is the main source for this isotope.

Evidence of the radioactive fallout in France due to the Fukushima nuclear accident

International Nuclear Information System (INIS)

Evrard, Olivier; Van Beek, Pieter; Gateuille, David; Pont, Véronique; Lefèvre, Irène; Lansard, Bruno

2012-01-01

Radioactive fallout due to the Fukushima reactor explosion in Japan was detected in environmental samples collected in France. The presence of 131 I in aerosols (200 ± 6 μBq m −3 ) collected at the Pic du Midi observatory, located at 2877 m altitude in the French Pyrénées, indicated that the Japanese radioactive cloud reached France between 22 and 29 March, i.e. less than two weeks after the initial emissions, as suggested by a 137 Cs/ 134 Cs ratio of 1.4. Cesium radioisotopes ( 134 Cs and 137 Cs) were not detected in this sample but they were present in the aerosol sample collected the next week, i.e. between 29 March and 05 April (about 10 μBq m −3 ). We also report 131 I activities measured in grass (1.1–11 Bq kg −1 ; fresh weight) and soil samples (0.4 Bq kg −1 ) collected in the Seine River basin between 30 March and 10 April. The 134 Cs from the damaged Fukushima power plant was also detected in grass collected in the Seine River basin between 31 March and 10 April (0.2–1.6 Bq kg −1 fresh weight, with a 137 Cs/ 134 Cs ratio close to 1, which is consistent with Fukushima radioactive release). Despite the installation of a network of nested stations to collect suspended matter in the upstream part of the Seine River basin, 131 I was only detected in suspended matter (4.5–60 Bq kg −1 ) collected at the most upstream stations between 30 March and 12 April. Neither 131 I nor 134 Cs has been detected in environmental samples since the end of April 2011, because of the rapid decay of 131 I and the very low activities of 134 Cs (about 400 times lower than after Chernobyl accident). - Highlights: ► Artificial radionuclides emitted by Fukushima power plant accident were detected in environmental samples collected in France. ► Radioactivity measurements on air filters obtained at the highest altitude in France. ► 131 I detected in grass, soil and sediment collected between 30 March and 12 April. ► 134 Cs detected in grass collected between

Radionuclide study of thyroid function in pediatrics, using sup(99m)Tc, /sup 123/I or /sup 131/I: 150 case-reports

Energy Technology Data Exchange (ETDEWEB)

Guillet, J.; Basse-Cathalinat, B.; Soubiran, G.; Blanquet, P. (Hopital Pellegrin, 33 - Bordeaux (France)); Guillet, G. (Johns Hopkins Medical Institutions, Baltimore, MD (USA). Div. of Nuclear Medicine)

1981-11-01

THe best radioisotope for in vivo thyroid investigations is the one which provides the highest quality scintigrams with the least radiation exposure. The choice of /sup 131/I, /sup 123/I or sup(99m)Tc in 150 children is discussed. Cases included 25 dysgenesis, 4 goiters with hypothyroidism, 56 goiters without thyroid dysfunction, 3 thyroiditis, and 11 cold nodules. When thyroid scanning is performed with /sup 131/I, the gland's radiation exposure is high. /sup 123/I is preferable since a fairly high activity can be obtained without delivering an excessive radiation dose. (approximately 2 rad to the thyroid for 50 microCi/m/sup 2/). sup(99m)Tc which is readily available is not a true iodine analog. It does not give a true picture of iodine metabolism. /sup 123/I was generally used in cases of hypothyroidism, goiter (whenever a defect in thyroid hormone synthesis was suspected) and hyperthyroidism. sup(99m)Tc was generally used in other cases. The low radiation doses delivered by these radioisotopes allows study of thyroid function in the neonate.

Development of a methodology to determine optimized therapeutic doses of {sup 131}I for the treatment of hyperthyroidism

Energy Technology Data Exchange (ETDEWEB)

Araujo, Francisco de; Santas, Bernardo Maranhao; Dantas, Ana Leticia Almeida; Lucena, Eder Augusto [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: faraujo@ird.gov.br; Melo, Rossana Corbo de; Rebelo, Ana Maria de Oliveira [Universidade Federal, Rio de Janeiro, RJ (Brazil). Faculdade de Medicina

2007-07-01

Several methods can be used to determine the activity of {sup 131}I to be administered for the treatment of hyperthyroidism. However, some of them do not take into consideration the dose absorbed by the thyroid, while others do not consider all the parameters necessary for dose calculation. The relationship between the dose absorbed by the thyroid and the activity administered depends basically on three parameters: mass of the organ, iodine uptake and effective half-life of iodine in the thyroid. Such parameters should be individually determined for each patient in order to optimize the administered activity. The objective of this work is to develop a methodology to evaluate therapeutic doses through the determination of biokinetic parameters and the activity of {sup 131}I deposited in the thyroid of patients submitted to the treatment of hyperthyroidism with {sup 131}I. A neck-thyroid phantom developed at the In Vivo Monitoring Laboratory of IRD, containing a known amount of {sup 131}I, was used to calibrate a scintillation camera and a uptake probe available at the Nuclear Medicine Center of the University Hospital of Rio de Janeiro. The optimization of the counting geometry was carried out by the determination of the characteristic curves of the view angle of the collimator-detector assembly. The calculation of the calibration factor of the scintillation camera allows the determination of activities in the thyroid of patients in pre-established time periods through a 48-hours uptake curve. The view angle of the collimator-detector assembly presented values compatible with the size of the organ for distances of 25 cm (uptake probe) and 45.8 cm (scintillation camera). The calibration factors (in cpm/kBq) and the associated uncertainty related to these distances were 39.3 {+-} 0.8 and 4.3 {+-} 0.2 respectively. The time period between 14 and 30 hours of the retention curve allows the calculation of the activity between those two points. It is concluded that the use

Radioisotope handling facilities and automation of radioisotope production

International Nuclear Information System (INIS)

2004-12-01

If a survey is made of the advances in radioisotope handling facilities, as well as the technical conditions and equipment used for radioisotope production, it can be observed that no fundamental changes in the design principles and technical conditions of conventional manufacture have happened over the last several years. Recent developments are mainly based on previous experience aimed at providing safer and more reliable operations, more sophisticated maintenance technology and radioactive waste disposal. In addition to the above observation, significant improvements have been made in the production conditions of radioisotopes intended for medical use, by establishing aseptic conditions with clean areas and isolators, as well as by introducing quality assurance as governing principle in the production of pharmaceutical grade radioactive products. Requirements of the good manufacturing practice (GMP) are increasingly complied with by improving the technical and organizational conditions, as well as data registration and documentation. Technical conditions required for the aseptic production of pharmaceuticals and those required for radioactive materials conflicting in some aspects are because of the contrasting contamination mechanisms and due consideration of the radiation safety. These can be resolved by combining protection methods developed for pharmaceuticals and radioactive materials, with the necessary compromise in some cases. Automation serves to decrease the radiation dose to the operator and environment as well as to ensure more reliable and precise radiochemical processing. Automation has mainly been introduced in the production of sealed sources and PET radiopharmaceuticals. PC controlled technologies ensure high reliability for the production and product quality, whilst providing automatic data acquisition and registration required by quality assurance. PC control is also useful in the operation of measuring instruments and in devices used for

Radioisotope Power Sources

International Nuclear Information System (INIS)

Culwell, J. P.

1963-01-01

The radioisotope power programme of the US Atomic Energy Commission has brought forth a whole new technology of the use of radioisotopes as energy sources in electric power generators. Radioisotope power systems are particularly suited for remote applications where long-lived, compact, reliable power is needed. Able to perform satisfactorily under extreme environmental conditions of temperature, sunlight and electromagnetic radiations, these ''atomic batteries'' are attractive power sources for remote data collecting devices, monitoring systems, satellites and other space missions. Radioisotopes used as fuels generally are either alpha or beta emitters. Alpha emitters are the preferable fuels but are more expensive and less available than beta fuels and are generally reserved for space applications. Beta fuels separated from reactor fission wastes are being used exclusively in land and sea applications at the present. It can be expected, however, that beta emitters such as stiontium-90 eventually will be used in space. Development work is being carried out on generators which will use mixed fission products as fuel. This fuel will be less expensive than the pure radioisotopes since the costs of isotope separation and purification are eliminated. Prototype thermoelectric generators, fuelled with strontium-90 and caesium-137, are now in operation or being developed for use in weather stations, marine navigation aids and deep sea monitoring devices. A plutonium-238 thermoelectric generator is in orbit operating as electric power source in a US Navy TRANSIT satellite. Generators are under development for use on US National Aeronautics and Space Administration missions. The large quantities of radioactivity involved in radioisotope power sources require that special attention be given to safety aspects of the units. Rigid safety requirements have been established and extensive tests have been conducted to insure that these systems can be employed without creating undue

Analysis of factors affecting the early hypothyroidism following 131I treatment of Graves' disease

International Nuclear Information System (INIS)

Tian Rong; Kuang Anren; Qin Weishi

2001-01-01

Objective: It is a retrospective study designed to evaluate the early therapeutic outcome of radioiodine therapy in patients with Graves' disease and determine whether the outcome of radioiodine therapy in Graves' disease depends on thyroid volume, function, thyreo-stasis, therapeutic dosage, 131 I uptake, age, sex, and absorbed doses by per gram of thyroid tissue. Methods: One year after treatment, 342 patients were divided into two groups according to whether there was hypothyroidism, t test and x 2 test were used to compare the variable parameters between the two groups. Results: 92.1% were cured with a single dose of 131 I, and 21.2% contracted hypothyroidism at 12 months after treatment. The outcome of treatment at 12 months depended on the volume of thyroid and the absorbed doses by per gram of thyroid tissue. And pretreatment with thyreo-stasis did not reduce the therapeutic efficacy of 131 I in hyperthyroidism if antithyroid drugs were discontinued at least 3 days before 131 I treatment. Conclusions: Since most hypothyroidism occurred in patients whose thyroid volume is small, appropriate reduction of target dose is recommended here for those patients

Iodine-131 therapy for parotid oncocytoma

Energy Technology Data Exchange (ETDEWEB)

Kosuda, S.; Ishikawa, M.; Tamura, K.; Mukai, M.; Kubo, A.; Hashimoto, S.

1988-06-01

We present a rare case of a patient with coexisting parotid oncocytoma and chronic thyroiditis who received two therapeutic doses of (/sup 131/I)iodide for a recurrent oncocytoma (oxyphilic granular cell adenoma), resulting in a definite reduction in tumor volume. We suggest that radioiodine therapy for a recurrent oncocytoma is an effective form of tumor therapy.

Assessment of methodology for 131I determination in workers exposed to incorporation

International Nuclear Information System (INIS)

Cerchetti, Maria L.; Arguelles, Maria G.

2005-01-01

In this work a technique used to monitor internal contamination of workers exposed to Iodine-131 incorporation from Radioisotope Production Plant was assessed. For the measurements of workers a NaI(Tl) EG and G ORTEC 905-1 were used in specific geometry, and data acquisition was controlled with Maestro TM software. Phantom has been used for calibration of efficiency of detectors placed in the same position as the real monitored person. Moreover, background counting was evaluated by statistical analysis for determination of protocol counting. The results obtained were analyzed under two models for calculating the decision threshold (Lc), and the minimum detectable activity (MDA), finally total uncertainty was calculated. Mean of efficiency was de 0.13% (RSD 6.7%) N = 43 D 6,7%, the MDA was 224 Bq (95% NC), and total propagated uncertainty was ± 13%. We obtained an effective evaluation of thyroid monitoring system for measurement of Iodine-131 in occupationally exposed persons. (author)

Report of the consultants' meeting on comparative laboratory evaluation of therapeutic radionuclides and radiopharmaceuticals

International Nuclear Information System (INIS)

1999-12-01

Therapeutic radiopharmaceuticals consist of two components - the radionuclide and the biological carrier. With regard to the radionuclide, an advantage of targeted radiotherapy is that there are a wide variety of radionuclides with different physical half-lives and radiation qualities that can be applied for this purpose. An important task is to select a radionuclide that is compatible with the needs of a particular clinical application. The identification of the ideal targeted radiotherapeutic for each potential clinical application is a difficult task because of the multitude of variables that must be considered, some relating to the radioisotope, and others to the biological carrier. Hence it is recommended that a Co-ordinated Research Programme be established by the Agency to enable participants to acquire and intercompare the methodological expertise to evaluate the relative merit of therapeutic radiopharmaceuticals. These studies will be performed using a model system selected either from those described in this report or a promising agent that has emerged in the time since this meeting. The molecular carrier will be labelled with 131 I, 125 I as well as other therapeutic radionuclides available to the participant (for example, 90 Y, 186 Re, 188 Re, 153 Sm, 166 Ho, 165 Dy). The potential radiopharmaceuticals will then be compared in a progression of studies evaluating biological integrity after labelling, internalisation and residualization of radioactivity in the tumour cell, in vitro cytotoxicity, tissue distribution, normal organ toxicity (determination of the maximum tolerated dose) and finally, therapeutic efficacy

Medical therapeutic effect of hyperthyroidism

International Nuclear Information System (INIS)

Lee, K.B.

1980-01-01

In order to compare the therapeutic effect as well as side effects between antithyroid therapy and radioiodine therapy in hyperthyroidism, the author evaluated 111 cases of hyperthyroidism which were composed of 57 patients with antithyroid treatment, 23 patients with combined treatment comprising of antithyroid and radioactive iodine ( 131 I) and 31 patients with treatment of 131 I alone. (author)

Use of radiation and radioisotopes for investigating metabolic diseases of animals in India

Energy Technology Data Exchange (ETDEWEB)

Arora, S P [National Dairy Research Inst., Karnal (India). Div. of Dairy Cattle Nutrition and Physiology

1980-03-01

In the last decade, radioisotopes have been used to investigate certain metabolic diseases of animals and radiation is being utilized to produce parasitic vaccines to vaccinate animals. Some studies in which radioisotopes have been used to investigate certain metabolic disorders are reviewed. In experiments where radioimmunoassay technique for the estimation of hormones, has been utilized, the results reveal that the animals on low level of nutrition show greater oestrous cycle lengths or even long anoestrous periods. On the other hand, irradiation has been used as a tool to produce vaccines as well as degradation of certain dietary molecules for increased utilization. A number of studies wherein /sup 35/S and /sup 15/N isotopes have been used, reveal that sulphur supplementation is essential for optimum utilization of nitrogen in the ratio of 1:10. There are certain antimetabolites in feed ingredients which affect endocrine function. Evidence indicates that high nitrate forages disturb thyroid function when sup(131)I is used to elucidate its secretion rate. Similarly certain toxic substances such as tannins have been shown to affect protein metabolism and phosphorus utilization when sup(32)P isotope is used in such studies. The use of radioisotopes has also been helpful to investigate the cause of ''Degnala'' disease prevalent in village cattle in certain states of India. With the help of sup(75)Se it has been possible to trace the metabolic disturbances which lead to the onset of this disease. Another deficiency disease, hyperkeratosis, has been shown to be caused not only because of vitamin A deficiency, but also because of zinc deficiency. The latter helps in the mobilization of a normal quantity of vitamin A from the liver into the blood vitamin A pool. There is wide scope for use of radioisotopes to investigate other metabolic diseases prevalent in livestock in this country.

Use of radiation and radioisotopes for investigating metabolic diseases of animals in India

International Nuclear Information System (INIS)

Arora, S.P.

1980-01-01

In the last one decade, radioisotopes are being used to investigate certain metabolic diseases of animals and radiations are being utilized to produce parasitic vaccines to vaccinate animals. Some studies in which radioisotopes have been used to investigate certain metabolic disorders are reviewed. In experiments, where radioimmunoassay technique for the estimation of hormones, has been utilized, the results reveal that the animals on low plane of nutrition show greater oestrous cycle lengths or even long anoestrous periods. On the other hand, irradiation has been used as a tool to produce vaccines as well as degradation of certain dietary molecules for increased utilization. A number of studies wherein 35 S and 15 N isotopes have been used, reveal that sulphur supplementation is essential for optimum utilization of nitrogen in the ratio of 1:10. There are certain antimetabolites in feed ingredients which affect endocrine function. Evidence indicates that high nitrate forages disturb thyroid function when sup(131)I is used to elucidate its secretion rate. Similarly certain toxic substances such as tannins have been shown to affect protein metabolism and phosphorus utilization when sup(32)P isotope is used in such studies. The use of radioisotopes have also been helpful to investigate the cause of ''Degnala'' disease prevalent in village cattle in certain states of India. With the help of sup(75)Se it has been possible to trace out the metabolic disturbances which lead to the onset of this disease. Another deficiency disease, hyperkeratosis, has been shown to be caused not only because of Vitamin A deficiency, but also because of zinc deficiency. The latter helps in the mobilization of normal quantity of vitamin A from the liver into the blood vitamin A pool. There is wide scope to use radioisotopes to investigate other metabolic diseases prevalent in livestock in this country. (auth.)

Evaluation of Continuous Stirred Tank Reactor Performance by Using Radioisotope Tracer

International Nuclear Information System (INIS)

Noor Anis Kundari; Djoko Marjanto; Ardhani Dyah W

2009-01-01

Research on performance evaluation of continuous stirred tank reactor (CSTR) using radioisotope tracer has been carried out. The aim of research is to assess a validity of assumption that stirring or mixing process in a CSTR is perfect. In order to follow the flow dynamics process of the fluid in the reactor, I-131 was used. The reactor was equipped with four baffles. The fluid/water leaving the reactor was sampled at 13 up to 1393 seconds and analysed its I-131 concentration. The performance of CSTR is expressed as dispersed number (D/uL) as function of retention time and Reynolds number under axial dispersed model. The experimental result show that the relation between the dispersion number and retention time is D/uL = 9X10 -4 (t s * ) 2 - 6.9X10 -1 (t s * ) + 148 and the dispersion number and Reynolds number is D/uL = 65.7 e 0.0003/Re . The dispersion number obtained were much higher than 0.01 that in between 11.08 up to 21.4. That mean the mixing process occurred in the CSTR can be assumed to be ideal. (author)

Assessment of 90Sr and 137Cs activity concentration in human tissues in Hungary following the Chernobyl accident

International Nuclear Information System (INIS)

Turai, I.; Sztanyik, B.L.

1997-01-01

Artificial radioisotope contamination of tissue samples of Hungarian citizens has been regularly monitored by our Institute since 1978. 90 Sr concentration of both extracted deciduous teeth and rib samples showed a slight but permanent tendency to decrease since then. 137 Cs content in the body of Hungarian individuals was monitored by whole body counter from the mid of 60s for about a decade while it became lower of the minimum detection limit (MDL). It could again be detected by in vivo measurements in May 1986, however, the 137 Cs content of human beings in Hungary fell below the detection limit within two years. Thus, the monitoring could only be continued by in vitro measuring of the 137 Cs activity concentration in human soft tissue samples

I131-meta-iodobenzylguanidine in the diagnosis and treatment of neural crest tumours

International Nuclear Information System (INIS)

Hoefnagel, C.A.; Hartog Jager, F.C.A. den; Taal, B.G.; Engelsman, E.; Kraker, J. de; Voute, P.A.

1988-01-01

Iodine-131-meta-iodobenzylguanidine (I-131-MIBG) was used for scintigraphic detection and therapy of neural crest tumours. The methodology of both techniques is described. Based upon experience with I-131-MIBG-scintigraphy in 170 patients with neural crest tumours, of whom 46 received multiple therapeutic doses of I-131-MIBG, and upon the cumulative reports in the literature, the role of I-131-MIBG in diagnosis and treatment of each of these diseases is indicated. I-131-MIBG-scintigraphy is one of the most sensitive and specific techniques for the diagnosis, staging and follow-up of phaeochromocytoma and neuroblastoma and I-131-MIBG-therapy may induce remission in a number of these patients. In carcinoid and medullary thyroid carcinoma the diagnostic sensitivity is less; however, once the diagnosis has been made, it is useful to establish that the tumour concentrates I-131-MIBG, to see if the patients at some point in time may be amenable to I-131-MIBG-therapy

Radioisotope studies utilizing a low level whole body counter and clinical applications of activation analysis. Progress report

International Nuclear Information System (INIS)

Brill, A.B.

1976-01-01

Design modifications in radioisotope scanners are discussed. Studies on the radiation dose distribution in patients from /sup 90m/Tc-albumin microspheres in the lungs, 59 Fe-citrate, 131 I-hippuran in kidney transplants, and /sup 99m/Tc-pyrophosphates are reported. Data on the levels of fallout 137 Co in normal individuals during 1975, as measured by whole-body counting, are reported. Results of studies on iodine metabolism in patients with hyperthyroidism and with T 3 -thyrotoxicosis during 131 I therapy with activities up to 17 mCi showed that the apparent volumes of distribution for different iodine compounds do not change appreciably during therapy in this dose range. Methods are described for measuring the content of Ca alone and Ca and P in bone tissues by transmission scanning using a 252 Cf neutron source for activation of Ca and P

Application of radioisotopes in pharmaceutical research

International Nuclear Information System (INIS)

Khujaev, S.

2004-01-01

Full text: To use of radioisotopes in the processes of receiving radiopharmaceutical diagnostic means it is widely know [1]. Radioactivity labeled chemical compounds, pharmacological kinetics of which allows one solving a concrete diagnostic problem in an organism are used in radio pharmaceutics. In spite of this choice of the radioisotope, possessing the most favorable nuclei-physical characteristics for it to be detected and minimization of beam loadings, be of great importance. Development of a method of introduction of a radioisotope also has important value, as it is included into chemical structure of a radiopharmaceutical preparation. One more way of use of radioisotopes in pharmaceutics is their use as a radioactive mark at a stage of creation of a new medical product. And in this case, all those moments, which are listed above, take place. Preparations labeling by radioisotopes are used basically for their studying pharmacological kinetics. In Institute of nuclear physics AS RU, in recent years, works are done on studying pharmacological kinetics of some new medical products, which have been synthesized in the Tashkent pharmaceutical institute. These preparations are on the basis of microelements with a complex set of properties possessing expressed biological activity and have great value in pharmaceutical science of Republic of Uzbekistan. Reception of labeled compounds of all preparations was carried out by a method of introduction of a radioisotope at a stage of their synthesis. The work presents the results of researches on synthesis and study of pharmacological kinetics of radioactively labeled preparations - PIRACIN, labeled by radioisotope 69m Zn; FERAMED, labeled by radioisotope 59 Fe; COBAVIT, labeled by radioisotope 57 Co; VUC, labeled by radioisotope 57 Co

Diagnosis and treatment of a carcinoid tumor using iodine-131 meta-iodobenzylguanidine

International Nuclear Information System (INIS)

Hoefnagel, C.A.; Den Hartog Jager, F.C.; Van Gennip, A.H.; Marcuse, H.R.; Taal, B.G.

1986-01-01

Scintigraphy using I-131 meta-iodobenzylguanidine has been introduced as an effective method to detect pheochromocytomas and neuroblastomas, and the radiopharmaceutical also is applied in therapy of these tumors. The authors present a case of a metastatic gastric carcinoid tumor, another neural crest tumor, concentrating I-131 MIBG, which was documented by conventional scintigraphy and SPECT in correlation with CT scans and colloid scintigrams of the liver. Two therapeutic attempts in this patient, using I-131 MIBG, are described. The metabolic basis of this phenomenon is discussed, and the importance of I-131 MIBG imaging in the detection of neural crest tumors is underlined

Internal contamination of nurses as a result of the therapeutic use of iodine-131

Energy Technology Data Exchange (ETDEWEB)

Termorshuizen, W; Gerritsen, A J.M.

1988-02-01

The internal contamination of nurses with sodium iodide-131 is studied in two different housing situations. Before moving, the therapy unit was an unventilated double room with a lock. In the new building, the unit consists of three single rooms and one double room with a lock and air conditioning. Also the concentration of iodine-131 in the air is measured. 2 figs.; 1 table.

Production of radioisotopes using accelerators

International Nuclear Information System (INIS)

Qaim, S.M.

1990-01-01

Accelerator produced radioisotopes find applications in many fields. Most of them are ideally suited for in-vivo studies of physiological functions. A brief review of various types of accelerators used for radioisotope production is given. The 'state of art' technology relevant to the production of radioisotopes is briefly discussed. Some of the recent advances in nuclear data measurements, target development, chemical processing and quality control are described. There appears to be a definite shift from multipurpose accelerators to dedicated machines, and greater emphasis is placed now on the production of radioisotopes with high radionuclidic purity by choosing a suitable nuclear reaction in a proper energy range. (author)

Evolution of 137Cs and 90Sr content of the main foodstuff in Bucharest area after the Chernobyl accident

International Nuclear Information System (INIS)

Toader, M.; Vasilache, R.A.

1997-01-01

Soon after the Chernobyl accident, the radioactive cloud, carrying the nuclides released into the atmosphere, reached Romania and, due to the rainy weather, an important fallout occurred over the Romanian territory. The most important contaminants for Romania were I 131 , Cs 134 , Cs 137 and Sr 90 . As in many other countries, in the first days, I 131 had the main contribution to the irradiation dose released to the population. After its decay, and the decay of other short-lived radionuclides, Cs 137 and Sr 90 remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. To assess the radioactive burden of foods, a long term, large scale survey was initiated at the National Institute of Hygiene and Public Health (INISP). These results were then used to assess the doses committed to cesium and strontium intake and the excedentary cancer risk for the population from Bucharest area

Metabolic comparison of radiolabeled aniline- and phenol-phthaleins with 131I

International Nuclear Information System (INIS)

Avcibasi, Ugur; Avcibasi, Nesibe; Unak, Turan; Unak, Perihan; Mueftueler, Fazilet Zuemruet; Yildirim, Yeliz; Dincalp, Haluk; Guemueser, Fikriye Guel; Dursun, Ebru Rueksen

2008-01-01

The metabolic comparison of aniline- and phenol-phthaleins radiolabeled with 131 I ( 131 I-APH and 131 I-PPH, respectively) has been investigated in this study. To compare the metabolic behavior of these phthaleins and their glucuronide conjugates radiolabeled with 131 I, scintigraphic and biodistributional techniques were applied using male Albino rabbits. The results obtained have shown that these compounds were successfully radioiodinated with a radioiodination yield of about 100%. Maximum uptakes of 131 I-APH and 131 I-PPH, which were metabolized as N- and O-glucuronides, were observed within 2 h in the bladder and in the small intestine, respectively. In the case of verification of considerably up taking of these compounds also by tumors developed in the small intestine and in the bladder tissues, these results can be expected to be encouraging to test these compounds, which will be radiolabeled with other radioiodines such as 125 I, 123 I and 124 I as imaging and therapeutic agents in nuclear medical applications

Metabolic comparison of radiolabeled aniline- and phenol-phthaleins with (131)I.

Science.gov (United States)

Avcibaşi, Uğur; Avcibaşi, Nesibe; Unak, Turan; Unak, Perihan; Müftüler, Fazilet Zümrüt; Yildirim, Yeliz; Dinçalp, Haluk; Gümüşer, Fikriye Gül; Dursun, Ebru Rükşen

2008-05-01

The metabolic comparison of aniline- and phenol-phthaleins radiolabeled with (131)I ((131)I-APH and (131)I-PPH, respectively) has been investigated in this study. To compare the metabolic behavior of these phthaleins and their glucuronide conjugates radiolabeled with (131)I, scintigraphic and biodistributional techniques were applied using male Albino rabbits. The results obtained have shown that these compounds were successfully radioiodinated with a radioiodination yield of about 100%. Maximum uptakes of (131)I-APH and (131)I-PPH, which were metabolized as N- and O-glucuronides, were observed within 2 h in the bladder and in the small intestine, respectively. In the case of verification of considerably up taking of these compounds also by tumors developed in the small intestine and in the bladder tissues, these results can be expected to be encouraging to test these compounds, which will be radiolabeled with other radioiodines such as (125)I, (123)I and (124)I as imaging and therapeutic agents in nuclear medical applications.

Activity calculation of radioisotopes in HFETR

International Nuclear Information System (INIS)

Liu Shuiqing

1996-12-01

The activity calculating method and formulas of seven kinds of radioisotopes for High Flux Engineering Test REactor (HFETR) are given. The perturbation of targets to neutron fluence rate is considered while targets are put into the neutron fluence rate field of reactor core. All perturbing factors of seven kinds of radioisotopes being used in HFETR are presented. After considering the perturbation, the calculating accuracy of radioisotope activity has been raised 10%. The given method and formulas have ended the history of all activities estimated by experiences, except for that of 60 Co, in the radioisotope production of HFETR. The conclusions are also useful and instructive for the production of radioisotopes in HFETR. (8 tabs.)

Retrospective reconstruction of Iodine-131 distribution through the analysis of Iodine-129

Science.gov (United States)

Matsuzaki, Hiroyuki; Muramatsu, Yasuyuki; Ohno, Takeshi; Mao, Wei

2017-09-01

Iodine-131 distribution released from the Fukushima Dai-ichi Nuclear Power Plant accident was reconstructed through the iodine-129 measurements. From nearly 1,000 surface soil samples iodine was extracted by the pyro hydrolysis method. Extracted iodine was then mixed with carrier, purified and finally collected as silver iodide. Silver iodide sample was pressed into the cathode holder and set at the ion source of the MALT facility, The University of Tokyo. The isotopic ratio 129I/127I was measured by means of Accelerator Mass Spectrometry. From 129I data obtained, 131I deposition map was constructed. There observed various fine structures in the map which could not estimated neither by the simulation nor 137Cs distribution.

Comparison of thyroid uptake of 131I capsule and solution in rabbits and graves disease patients

International Nuclear Information System (INIS)

Zhou Xinjian; Li Fang; Lu Jingqiao; Chen Daming; Zhang Ruilin

2002-01-01

Objective: To observe the difference between thyroid uptake rates (TUR) of 131 I capsule and solution in rabbits and Graves disease patients. Methods: Part one: 6 rabbits randomized into two groups received capsule or solution of 131 I 7.4 MBq. Then with SPECT scintigraphy 2,4,6 and 24 h thyroid pure counts in percentage of stomach counts (first frame) were determined. Part two: 1) Measured 131 I capsule standard. 2) 104 patients with Graves disease were administered tracing and therapeutic dose of 131 I capsule (capsule group), 118 of 131 I solution (solution group). Compared the tracing and therapeutic 131 I TUR at 24 h. Results: Part one: There were no significant difference at 2,4,6,24 h TUR between capsule and solution group. For 1 case the maximum TUR was at 6 h in capsule group and 2 cases in solution groups. Part two: 1) For the 131 I capsule administered immediately after being dissolved in 30 mL of water, the activity counts measured were higher by (13.8 +- 2.8)% than it was administered directly, t8.97, P 0.05) and in solution group were (71.3 +- 12.3)% and (65.1 +- 13.0)% (t = 3.82, P 131 I capsule standard should be dissolved before being measured. 3) 131 I capsules can be used as a standard formulation for Graves disease patients. 4) The dose of 131 I should be increased as tracer TUR is larger than 80.0%

Assessment of soil redistribution rates by 137Cs and 210Pbex in a typical Malagasy agricultural field

International Nuclear Information System (INIS)

Rabesiranana, N.; Rasolonirina, M.; Solonjara, A.F.; Ravoson, H.N.; Raoelina Andriambololona; Mabit, L.

2016-01-01

Soil degradation processes affect more than one-third of the Malagasy territory and are considered as the major environmental threat impacting the natural resources of the island. This innovative study reports about a pioneer test and use of radio-isotopic techniques (i.e. Cs-137 and Pb-210ex) under Madagascar agroclimatic condition to evaluate soil erosion magnitude. This preliminary investigation has been conducted in a small agricultural field situated in the eastern central highland of Madagascar, 40 km East from Antananarivo. Both anthropogenic Cs-137 and geogenic Pb-210 soil tracers provided similar results highlighting soil erosion rates reaching locally 18 t ha −1  yr −1, a level almost two times higher than the sustainable soil loss rate under Madagascar agroclimatic condition. The sediment delivery ratio established with both radiotracers was above 80% indicating that most of the mobilized sediment exits the field. Assessing soil erosion rate through fallout radionuclides in Madagascar is a first step towards an efficient land and water resource management policy to optimise the effectiveness of future agricultural soil conservation practices. - Highlights: • A pioneer test of radioisotopic techniques under Madagascar agroclimatic condition for estimating soil erosion magnitude. • Cs-137 and Pb-210 ex Mass Balance Models (MBM) conjointly used to highlight timescale discrimination of erosion process. • Timescale discrimination suggests significant increase of erosion magnitude during the last 50 years. • Estimated erosion rates above 10 t ha −1 yr −1 indicate a clear threat for the sustainability of Malagasy soil resources. • Findings indicate the potential of using jointly Cs-137 and Pb-210 ex under local agroecological conditions.

Intercomparison of 131I activity measurements in nuclear medicine

International Nuclear Information System (INIS)

Kim, G. Y.; Yang, H. K.; Lim, C. I.; Lee, H. K.; Jeong, H. K.

2004-01-01

Activity measurements in nuclear medicine using a dose calibrator have been performed for several decades and their reliability has varied. To minimise the radiation dose to patients with radionuclides, it is necessary to ensure that the sample administered is accurately assayed. Recognizing the importance of intercomparison in nuclear medicine and the need to make access to activity standards traceable to the international measurement system, the KFDA, as a national secondary standard dosimetry laboratory (SSDL), started an intercomparison program in 2002. This program was initiated by survey to all nuclear medicine centres regarding general information about their dose calibrators, radioisotopes etc. 71 nuclear medicine centres (79 dose calibrators) participated in the intercomparison program with 131 I isotope. To assess the accuracy of clinical measurements of the activity of 131 I solutions and to determine the reason for the disagreement, an intercomparison was conducted using 4 ml aliquots in 10 ml P6 vial with a total activity in the region of 10 -20 MBq. The reference time of decay for all solutions was 0:00 on 25 September 2002. The half-life used was 8.04 days. For the evaluation of solution in KFDA, a sealed, high pressure and re-entrant ionisation chamber, NPL-CRC radionuclide calibrators were used. The verification of our calibration quality was by means of a comparison with the Korea Primary Standard Laboratory (KRISS). The activity ratio of KFDA to KRISS for the 131 I solutions is 1.011. The difference between the value quoted by the clinic, A hospital and the value obtained by the KFDA, A KFDA , is expressed as a percent deviation, i.e. DEV(%) 100x(A hospital -A KFDA )/A KFDA . From the data obtained it was found that 61% of the calibrators showed a deviation within +/-5%; 23% had a deviation in the range 5% 131 I solution activity measurements, using dose calibrators in Koreas, and also to provide the participants with a traceable standard to

Radioablative therapy with Iodine-131 on a patient with thyroid cancer and chronic renal failure in hemodialysis first experience in Peru

International Nuclear Information System (INIS)

Apaza Veliz, D. G.; Herrera Vera, R. D.; Cardenas Abarca, C. A.; Oporto Gonzales, C. A.; Aguilar Ramírez, C.; Urquizo Baldomero, R. M.; Vega Ramírez, J. L.

2016-01-01

The Iodine-131 (I-131) is a radioisotope used as a standard treatment for radioablation of thyroid remnants. Among thyroid cancer patients, the ones undergoing hemodialysis represent a specific group. The dose of I-131 is given orally to these patients, part of it is absorbed by the thyroid remnants and the rest of it, largely not incorporated, is excreted primarily by renal excretion. The use of a high dose of radioactivity in the process, and the inability of excretion, represents a high risk of exposure to the patient, medical staff and hemodialysis equipment. This work describes the procedure applied on the radioablation therapy for thyroid cancer while receiving hemodialysis, minimizing the risks for the patient and the staff involved. This clinical procedure will establish the dosimetric measures, a plan on radiation protection and a treatment protocol for this specific type of patients.

Radioablative therapy with Iodine-131 on a patient with thyroid cancer and chronic renal failure in hemodialysis first experience in Peru

Energy Technology Data Exchange (ETDEWEB)

Apaza Veliz, D. G., E-mail: dgav02@gmail.com [Hospital Nacional Carlos Alberto Seguin Escobedo, Servicio de Medicina Nuclear, Arequipa, Perú, Universidad Nacional de San Agustín de Arequipa, Escuela de Física, Arequipa (Peru); Herrera Vera, R. D.; Cardenas Abarca, C. A.; Oporto Gonzales, C. A.; Aguilar Ramírez, C.; Urquizo Baldomero, R. M. [Hospital Nacional Carlos Alberto Seguin Escobedo, Servicio de Medicina Nuclear, Arequipa (Peru); Vega Ramírez, J. L. [Universidad Nacional de San Agustín de Arequipa, Escuela de Física, Arequipa (Peru)

2016-07-07

The Iodine-131 (I-131) is a radioisotope used as a standard treatment for radioablation of thyroid remnants. Among thyroid cancer patients, the ones undergoing hemodialysis represent a specific group. The dose of I-131 is given orally to these patients, part of it is absorbed by the thyroid remnants and the rest of it, largely not incorporated, is excreted primarily by renal excretion. The use of a high dose of radioactivity in the process, and the inability of excretion, represents a high risk of exposure to the patient, medical staff and hemodialysis equipment. This work describes the procedure applied on the radioablation therapy for thyroid cancer while receiving hemodialysis, minimizing the risks for the patient and the staff involved. This clinical procedure will establish the dosimetric measures, a plan on radiation protection and a treatment protocol for this specific type of patients.

Radioablative therapy with Iodine-131 on a patient with thyroid cancer and chronic renal failure in hemodialysis first experience in Peru

Science.gov (United States)

Apaza Veliz, D. G.; Herrera Vera, R. D.; Cardenas Abarca, C. A.; Oporto Gonzales, C. A.; Aguilar Ramírez, C.; Vega Ramírez, J. L.; Urquizo Baldomero, R. M.

2016-07-01

The Iodine-131 (I-131) is a radioisotope used as a standard treatment for radioablation of thyroid remnants. Among thyroid cancer patients, the ones undergoing hemodialysis represent a specific group. The dose of I-131 is given orally to these patients, part of it is absorbed by the thyroid remnants and the rest of it, largely not incorporated, is excreted primarily by renal excretion. The use of a high dose of radioactivity in the process, and the inability of excretion, represents a high risk of exposure to the patient, medical staff and hemodialysis equipment. This work describes the procedure applied on the radioablation therapy for thyroid cancer while receiving hemodialysis, minimizing the risks for the patient and the staff involved. This clinical procedure will establish the dosimetric measures, a plan on radiation protection and a treatment protocol for this specific type of patients.

The curative effect analysis of 131I-therapy on patients with Graves' disease

International Nuclear Information System (INIS)

Cui Qin; Lu Shujun; Lu Tianhe

2002-01-01

To investigate the curative effect of 131 I-therapy on Graves' disease, the authors analyse conditions of patients who have received 131 I-therapy (n -674). These results showed that the incidence of fully recover, improve, Graves' disease and invalid is 80.11%, 7.28%, 11.87% and 0.74% respectively. Therefore, 131 I-therapy on Graves' disease is convenient. It has little side effect, low cost and better curative effect, it is one of the best therapeutic methods to treat hyperthyroidism

Charged particle cross-section database for medical radioisotope production: diagnostic radioisotopes and monitor reactions. Final report of a co-ordinated research project

International Nuclear Information System (INIS)

2001-05-01

Medical applications of nuclear radiation are of considerable interest to the IAEA. Cyclotrons and accelerators, available in recent years in an increasing number of countries, are being used for the production of radioisotopes for both diagnostic and therapeutic purposes. The physical basis of this production is described through interaction of charged particles, such as protons, deuterons and alphas, with matter. These processes have to be well understood in order to produce radioisotopes in an efficient and clean manner. In addition to medical radioisotope production, reactions with low energy charged particles are of primary importance for two major applications. Techniques of ion beam analysis use many specific reactions to identify material properties, and in nuclear astrophysics there is interest in numerous reaction rates to understand nucleosynthesis in the Universe. A large number of medically oriented cyclotrons have been running in North America, western Europe and Japan for more than two decades. In recent years, 30-40 MeV cyclotrons and smaller cyclotrons (E p < 20 MeV) have been installed in several countries. Although the production methods are well established, there are no evaluated and recommended nuclear data sets available. The need for standardization was thus imminent. This was pointed out at three IAEA meetings. Based on the recommendations made at these meetings, the IAEA decided to undertake and organize the Co-ordinated Research Project (CRP) on Development of Reference Charged Particle Cross-Section Database for Medical Radioisotope Production. The project was initiated in 1995. It focused on radioisotopes for diagnostic purposes and on the related beam monitor reactions in order to meet current needs. It constituted the first major international effort dedicated to standardization of nuclear data for radioisotope production. It covered the following areas: Compilation of data on the most important reactions for monitoring light ion

Medical radioisotopes for the next century

International Nuclear Information System (INIS)

Carr, S.W.

1999-01-01

Radioisotopes are widely used in medicine (Nuclear Medicine) for diagnosis, palliation and therapy of heart disease, cancer, muscoskeletal and neurological conditions. The radioisotopes used are both reactor and cyclotron produced. The utilisation is currently growing and is expected to continue to grow over the next 10-20 years. The combination of radioisotope and delivery vehicle can be designed to meet the intended end use. This paper will deal with the main approaches to the use of radioisotopes for Nuclear medicine ad future prospects for the area

Radioisotopes in industry

International Nuclear Information System (INIS)

Popple, B.N.

1977-01-01

The author explains clearly what is radiography, enumerates four major factors in considering a practical source to use namely half-life, penetrating power, half value layer and specific activity and also the advantages and disadvantages in using isotopes. Common radioisotopes used in industrial radiography are iridium, cesium, cobalt and thulium. Main uses of the radioisotopes are for radiographic testing like welding castings, forgoings etc.; thickness, level or density measurement and tracing. (RTD)

Kinetics of Cs adsorption on soils with different mineralogical composition

International Nuclear Information System (INIS)

Nakao, Atsushi; Funakawa, Shinya; Kosaki, Takashi

2004-01-01

137 Cs is one of the main radioisotopes released into the environment by nuclear powerstation accidents (e.g. Chernobyl) and nuclear weapons tests. Many studies have shown that Cs tends to remain at surface soils due to the high adsorption selectivity of clay minerals for this element. This behavior of the Cs + ion is, however, assumed to vary significantly depending on the mineralogical composition of the soil. The main objective of this study is to analyze the kinetics of Cs adsorption on soils with different mineralogical composition. Soil samples used in this study were Mollisols (Um) and Alfisols (Ua) from Ukraine, Ultisols (Tu) from Thailand and Spodosols (Js) from Japan. The dominant clay species of these soils are montmorillonite (Um, Ua), kaolinite and mica (Tu) and beidellite (Js). The rates of Cs adsorption and Ca or K desorption were measured using a continuous flow method. Soil samples that were previously saturated with Ca 2+ were leached with a 0.75 mmol/l Cs + solution at a constant rate of 2.0 ml/min. The leachate was collected every 10 minutes and the concentrations of Cs + , Ca 2+ and K + of each aliquot were measured by atomic adsorption spectrophotometry (Cs + , Ca 2+ ) and flame spectrophotometry (K + ). The datasets obtained were simulated using the first order kinetic model: y = a(1 - exp(-kt)), where a is the adsorption (desorption) maximum and k the rate constant. It is here assumed that Ca 2+ is desorbed from cation exchange sites and K + desorbed from the frayed edges of micaceous minerals. The values of a obtained for both Cs adsorption and Ca desorption was in the order Js>Um>Tu>Ua, whereas the values of k were in the order Tu>Ua>Um>Js. This result reflects the values of permanent negative charge of clays which are originated from the substitution of cations in the structure of 2:1 clay minerals. The value of a for K + desorption was, however, highest in Tu, suggesting that the values of Cs + -exchangeable K + correspond to the amount

Comparative study of conventional PAH and inulin clearance and slope clearance of 131I-o-hippuric acid and 51Cr-EDTA

International Nuclear Information System (INIS)

Berghaeuser, H.

1981-01-01

''Classic'' PAH and inulin clearance were determined in 81 patients with renal anomalies or renal diseases of different genesis and severity. In addition, radioisotope nephrography was carried out after administration of I-131-o-hippuric acid, followed by administration of Cr-51-EDTA. The activity decrease was recorded by a sensor located over the patient's right shoulder; the activities of a serum sample and of the urine excreted after 21 or 31 min were measured, and the findings were compared with those of the classic method. The clearance data calculated on the basis of the soulder measurements were hardly compatible with those of the conventional method in the case of 131 I-o-hippuric acid (r=0.54) and totally incompatible in the case of 51 Cr-EDTA. This means that the method described by Oberhausen is the only accurate method available for a quantitative assessment of the renal function on the basis of measurements of the activity decrease in the body. The activity of urine excreted after 31 min ( 131 I-hippuric acid:r=0.992, 51 Cr-EDTA:r=0.79) is a sufficiently accurate parameter although it is inaccurate at PAH clearance, values > 130 ml/min and inulin clearance values > 30 ml/min. Of the many parameters of radioisotope nephrogram curves, in the case of 131 I-o-hippuric acid only the parameters related to the ascent between 48 and 120 sec or to the secant ascent yield sufficient quantitative information for certain functional regions (r=0.9 resp. r=0.93). In the case of 51 Cr-EDTA, semiquantitative information on the renal function can be obtained by constructing secants on the nephrogram curves (r=0.7 resp. r=0.72). Here as in the case of 131 I-hippuric acid, the contribution of each kidney can be determined individually from the functional analysis of both kidneys. (orig.) [de

Normal values of iodine - 131 uptake in 24 hours, in Rio Grande do Norte, Brazil

International Nuclear Information System (INIS)

Oliveira Filho, T.F. de; Oliveira, C.F.F. de

Thorough clinical exams on all patients come to the radioisotope Laboratory at UFRN, where carried out attempting to select those patients with thyroids considered to be clinically normal. After wayne tests for hypo and hyperthyroidism were carried out, 100 patients were considered to be fit for the research. All of them had an impalpable and asympitomatic thyroid. Waynes clinical indices were precisely revealed in 93% of cases. It was concluded that the normal values of uptake of 131 I during the 24 hours in RGN varied between 14% and 44% [pt

Radioisotope requirements and usage in the radiopharmaceutical industry

International Nuclear Information System (INIS)

Langton, M.A.

1995-01-01

Radioisotopes are used extensively in many different productive and beneficial human endeavors. Amersham International, a U.K.-based company originating in the British Scientific Civil Service during World War II, has been actively involved in many of these activities for more than 50 yr. Today they are one of the world's largest suppliers of radioactive compounds and scaled radiation sources for use in industrial quality and safety assurance, life science research, and medicine. This paper outlines one of these applications: the use of radioisotopes as radiopharmaceuticals. Radiopharmaceuticals are radioactive nuclides and labeled compounds that have been developed for the diagnosis and treatment of (human) disease. They are manufactured via highly controlled processes and have gone through regulatory scrutiny and approval far in excess of other radioisotopes used in other applications. Radiopharmaceuticals can be conveniently split into two categories. One type is simply an active analog that mimics the physiological behavior of its inactive counterpart in the body. The other involves an actual pharmacological compound that exhibits the desired physiological behavior, which is then labeled with a radionuclide suitable for either imaging or the delivery of a therapeutic radiation dose as appropriate but which plays no part in the mechanism of action of the drug. The latter type, which is the more common of the two, can be supplied either as an active compounded product or as a open-quotes cold kit,close quotes which is then labeled with the appropriate radiopharmaceutical-grade radionuclide to yield the final product

Metabolism of the radioisotopes contained in the radioactive ashes obtained from the No. 5 Fukuryu Maru

Energy Technology Data Exchange (ETDEWEB)

Kikuchi, T; Wakisaka, G; Kono, T; Goto, H; Akagi, H; Yamamasu, T; Sugawa, I

1954-01-01

Among the radioisotopes 141, 144 Ce obtained by separation from ashes on the ship, i.e., /sup 91/Y, /sup 141,144/Ce, Pr/sup 144/, /sup 45/Ca, sup/ 89, 90/Sr, /sup 103, 106/RU, /sup 106/Rh, /sup 95/Zr, /sup 95/Nb, /sup 131/I, Sr, Ca, and Y were accumulated chiefly in the bones of adult mice, and the elimination of radio-Sr from there was very slow. When administered by mouth, radio-Sr and radio-Ca were readily absorbed from the digestive tract, while the absorption of radio-Y from the tract was poor.

Medical research with radioisotopes in Greece

Energy Technology Data Exchange (ETDEWEB)

Belcher, E H [Post-graduate Medical School, Hammersmith, London (United Kingdom)

1961-07-15

An important program of research into the nature and causes of congenital haemolytic anaemias, notably the disease known as Mediterranean anaemia or Thalassaemia, which is a serious medical problem in the Mediterranean countries, is at present being carried out in the Department of Clinical Therapeutics of the University of Athens under a research contract awarded by the International Atomic Energy Agency. This program is concerned with diseases in which there is an inherited defect or abnormality in the production of haemoglobin, the iron-containing pigment of the red blood cells which is responsible for the carriage of oxygen in the blood. Two techniques have been widely used in the studies at the University of Athens. In the first of these, a radioisotope of iron, iron-59, is used to follow iron metabolism and haemoglobin production. Iron metabolism in the body is concerned largely with the synthesis and breakdown of haemoglobin, which consists of a protein, globin, linked to an iron containing substance, haeme. The second technique makes use of a radioisotope of chromium, chromium-51, to study the fate of the red cells in the blood. By performing simultaneous studies with iron- 59 and chromium-51, a detailed picture of haemoglobin synthesis and red cell production and destruction can be built up. Such investigations have been invaluable in establishing the characteristic patterns of different congenital haemolytic anaemias.

Radioimmunotherapy of human colon cancer xenografts by using 131I labeled-CAb1 F(ab')2

International Nuclear Information System (INIS)

Li Ling; Xu Huiyun; Mi Li; Bian Huijie; Qin Jun; Xiong Hua; Feng Qiang; Wen Ning; Tian Rong; Xu Liqing; Shen Xiaomei; Tang Hao; Chen Zhinan

2006-01-01

Purpose: Therapeutic efficacy, suitable dose, and administration times of 131 I-CAb 1 F(ab') 2 , a new monoclonal antibody therapeutics specifically directed against a cell surface-associated glycoprotein of colon cancer, were investigated in this article. Methods and Materials: In human colon cancer xenografts, 131 I-CAb 1 F(ab') 2 at the dose of 125 μCi, 375 μCi, and 1125 μCi were administrated intraperitoneally on Days 6 and 18 after implantation of HR8348 cells with CAb 1 high reactivity. Survival time and tumor growth inhibition rate were used to evaluate the efficacy and safety of 131 I-CAb 1 F(ab') 2 in treatment of colon cancer xenografts. Results: Treatment of 125, 375, and 1125 μCi 131 I-CAb1 F(ab') 2 did not significantly decrease the mean survival time of nude mice when compared with nontreated groups (p = 0.276, 0.865, 0.582, respectively). Moreover, the mean survival times of nude mice receiving 375 μCi and 1125 μCi 131 I-CAb1 F(ab') 2 were significantly longer than that of 5-FU-treated groups (p 0.018 and 0.042). Tumor growth inhibition rates of the first therapy were 35.67% and 41.37%, with corresponding 131 I-labeled antibody dosage of 375 μCi and 1125 μCi. After single attack dosage, second reinforcement therapy may rise efficacy significantly. Tumor growth inhibition rates of 125 μCi, 375 μCi, and 1125 μCi 131 I-labeled antibody on Day 20 posttherapy were 42.65%, 56.56%, and 84.41%, respectively. Histopathology examination revealed that tissue necrosis of various degrees was found in 131 I-CAb1 F(ab') 2 -treated groups. Conclusion: 131 I-CAb 1 F(ab') 2 is safe and effective for colon cancer. It may be a novel and potentially adjuvant therapeutics for colon cancer

Role of radioisotopes in the study of insect pests

International Nuclear Information System (INIS)

Mansour, M.

2013-01-01

Although the use of nuclear techniques, particularly radioisotopes, in entomological research is less than a century old, the contribution of radioisotopes to the science of studying insects (Entomology) is indispensable. In fact, radioisotopes provided a very important and sometimes a unique tool for solving many research problems in entomology. This article discusses the most important and widely used applications of radioisotopes in studying insect pests. In particular, it concentrates on the subject of radioisotopes used in entomological research, methods of labeling insect with radioisotopes, half life of radioisotopes, and the role of radioisotopes in physiological, ecological, biological and behavioral studies of insects. (author)

Therapeutic administration of 131I for differentiated thyroid cancer, radiation dose to ovaries and outcome of pregnancies

International Nuclear Information System (INIS)

Garsi, Jerome-Philippe; Rubino, Carole; Labbe, Martine; Vathaire, Florent de; Schlumberger, Martin; Ricard, Marcel; Ceccarelli, Claudia; Schvartz, Claire; Henri- Amar, Michel; Bardet, Stephane

2008-01-01

Full text: Background: Radiation is known to be mutagenic. In thyroid cancer treatment, 131 I is usually administered, for the first treatment, at a 3.7 GMBq activity, corresponding to an estimated mean radiation dose of 140 mGy to the ovaries. However data on the effects of 131 I therapy on pregnancy outcomes, especially untoward, are scarce. Methods: Data on 2673 pregnancies were obtained by interviewing female patients treated for thyroid carcinoma who had not received external radiation to the ovaries, in three French hospitals and one Italian hospital. Results: The incidence of miscarriages was 10 % before any treatment for thyroid cancer; this percentage increased after surgery for thyroid cancer, both before (20 %) and after (19 %) 131 I treatment, with no variation according to the cumulative dose. Miscarriages were not significantly more frequent in women treated with 131 I during the year before conception, even in subjects who had received more than 370 MBq during that year, as compared to women never treated with 131 I. The incidence of stillbirths, preterm births, a low birth weight, congenital malformation and death during the first year of life was not significantly different before or after 131 I therapy. The incidence of thyroid and non thyroidal cancers was similar in children born either before or after the mother's exposure to 131 I. Conclusion: In our data, we found no evidence that exposure to 131 I affects the outcome of subsequent pregnancies and offspring. Whether the number of malformations, or thyroid and non thyroidal cancers are related to gonadal irradiation remains to be established. Our findings allowed us to fuel the debate on the doubling dose: the concept is still heatedly debated and the value of 1 Gy as the doubling dose in humans should be rediscussed. (author)

Design of radioisotope power systems facility

International Nuclear Information System (INIS)

Eschenbaum, R.C.; Wiemers, M.J.

1991-01-01

Radioisotope power systems currently produced for the U.S. Department of Energy Office of Special Applications by the Mound Laboratory at Miamisburg, Ohio, have been used in a variety of configurations by the Department of Defense and the National Aeronautics and Space Administration. A forecast of fugure radioisotope power systems requirements showed a need for an increased production rate beyond the capability of the existing Mound Laboratory. Westinghouse Hanford Company is modifying the Fuels and Materials Examination Facility on the Hanford Site near Richland, Washington, to install the new Radioisotope Power Systems Facility for assembling future radioisotope power systems. The facility is currently being prepared to assemble the radioisotope thermoelectric generators required by the National Aeronautics and Space Administration missions for Comet Rendezvous Asteroid Flyby in 1995 and Cassini, an investigation of Saturn and its moons, in 1996

Radioisotope Power Supply, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — Between 1998 and 2003, Hi-Z Technology developed and built a 40 mW radioisotope power supply (RPS) that used a 1 watt radioisotope heater unit (RHU) as the energy...

The study of labeling with Iodine-131 of monoclonal antibody anti-CD20 used for the treatment of non-Hodgkin lymphoma

International Nuclear Information System (INIS)

Akanji, Akinkunmi Ganiyu

2006-01-01

Lymphomas are malignancies of the lymphatic system, described by Thomas Hodgkin in 1932. Traditionally, lymphomas are classified in two basic groups: Hodgkin disease and non-Hodgkin lymphoma (NHL). Patients with NHL were earlier treated with radiotherapy alone or in combination with immunotherapy using monoclonal antibody anti-CD20 (ex., Rituximab-Mabthera, Roche). However, Radioimmunotherapy is a new modality of treatment for patients with NHL, in which cytotoxic radiation from therapeutic radioisotopes is delivered to tumors through monoclonal antibodies. This study focused on labeling conditions of monoclonal antibody anti-CD20 (Rituximab-Mabthera, Roche) with iodine-131, by direct radioiodination method using Chloramine-T as oxidizing agent. Labeling parameters investigated were: Radiochemical purity (RP), method of purification, incubation time, antibody mass, oxidative agent mass, stability in vitro, stability in vivo, immunoreactivity and biological distribution performed in normal Swiss mouse. Product of high radiochemical purity was obtained with no notable difference between the methods applied. No clear evidence of direct influence of incubation time on radiochemical purity of the labeled antibody was observed. Whereas, a clear evidence of direct influence of activity on radiochemical purity of the labeled antibody was observed when antibody mass was varied. After purification, the labeled product presented radiochemical purity of approximately 100 %. Product of superior radiochemical yield was observed when standard condition of labeling was used. The labeled product presented variation in radiochemical purity using five different stabilizer conditions. The condition in which gentisic acid was combined with freeze appears more suitable and capable of minimizing autoradiolysis of the antibody labeled with high therapeutic activity of iodine-131. The labeled product presented low immunoreactivity when compared to the literature. Biological distribution in

The study of labeling with iodine-131 of monoclonal antibody anti-CD20 used for the treatment of non-Hodgkin lymphoma

International Nuclear Information System (INIS)

Akanji, Akinkunmi Ganiyu

2006-01-01

Lymphomas are malignancies of the lymphatic system, described by Thomas Hodgkin in 1932. Traditionally, lymphomas are classified in two basic groups: Hodgkin disease and non-Hodgkin lymphoma (NHL). Patients with NHL were earlier treated with radiotherapy alone or in combination with immunotherapy using monoclonal antibody anti-CD20 (ex., Rituximab-Mabthera, Roche). However, Radioimmunotherapy is a new modality of treatment for patients with NHL, in which cytotoxic radiation from therapeutic radioisotopes is delivered to tumors through monoclonal antibodies. This study focused on labeling conditions of monoclonal anti-CD20 (ex., Rituximab-Mabthera, Roche) with iodine-131, by direct radioiodination method using Chloramine-T as oxidizing agent. Labeling parameters investigated were: Radiochemical purity (RP), method of purification, incubation time, antibody mass, oxidative agent mass, stability in vitro, immunoreactivity and biological distribution performed in normal Swiss mouse. Product of high radiochemical purity was obtained with no notable difference between the methods applied. No clear evidence of direct influence of incubation time on radiochemical purity of the labeled antibody was observed. Whereas, a clear evidence of direct influence of activity on radiochemical purity of the labeled antibody was varied. After purification the labeled product presented radiochemical purity of approximately 100 %. Product of superior radiochemical yield was observed when standard condition of labeling was used. The labeled product presented variation in radiochemical purity using five different stabilizer conditions. The condition in which gentisic acid combined with freeze appears more suitable and capable of minimizing autoradiolysis of the antibody labeled with freeze appears more suitable and capable of minimizing autoradiolysis of the antibody labeled with high therapeutic activity of iodine-131. The labeled product presented low immunoreactivity when compared to the

Facilities for Research and Development of Medical Radioisotopes

International Nuclear Information System (INIS)

Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

2003-03-01

This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value

Radioisotope detection and dating with accelerators

Energy Technology Data Exchange (ETDEWEB)

Mast, T S; Muller, R A [California Univ., Berkeley (USA). Lawrence Berkeley Lab.

1980-07-01

The status of the new technique of high energy mass spectrometry is reviewed. This sensitive method of measuring isotope concentrations has been applied to the detection of rare radioisotopes used for age estimation. The techniques used to select and identify the individual radioisotope atoms in a sample are described and then the status of the radioisotope measurements and their applications is reviewed.

Study to produce polymer gel for decontamination on the surface of steel, ceramic, plastic, glass

International Nuclear Information System (INIS)

Pham Quynh Luong; Nguyen Van Chinh; Nguyen Thu Trang; Nguyen An Thai; Nguyen Dinh Lam

2015-01-01

Strippable polymer coating is one of the methods for effective surface decontamination. A gel solution of a water soluble polymer, preferably polyvinyl alcohol (PVA) and chelating agent is applied to remove radioisotopes of Cs"1"3"7, Sr"8"5, I"1"3"1, P"3"2 and Tc"9"9"m on the surface of stainless steel, mild steel, ceramic, PVC plastic. After cleaning is completed, the gel solution is dried, formed a strong thin film, which is easily peeled off from a contaminated surface and can be disposed of as radioactive solid waste. Decontamination efficient of this gel polymer for radioisotopes have been studied on the surfaces and compared with Decongel 1101. The influence of decontamination agents, activity, film thickness to decontamination factor have been studied. The infrared spectrophotometer has been conducted to study mechanism of the decontamination for this radioisotope. (author)

{sup 177}Lu- labeled MOv18 as compared to {sup 131}I- or {sup 90}Y-labeled MOv18 has the better therapeutic effect in eradication of alpha folate receptor-expressing tumor xenografts

Energy Technology Data Exchange (ETDEWEB)

Zacchetti, Alberto [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Coliva, Angela [Department of Imaging and Nuclear Medicine, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Luison, Elena [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Seregni, Ettore; Bombardieri, Emilio [Department of Imaging and Nuclear Medicine, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Giussani, Augusto [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Neuherberg (Germany); Figini, Mariangela [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy); Canevari, Silvana [Unit of Molecular Therapies, Department of Experimental Oncology and Laboratories, Fondazione IRCCS Istituto Nazionale dei Tumori, Milan 20133 (Italy)], E-mail: silvana.canevari@istitutotumori.mi.it

2009-10-15

Introduction: The mouse monoclonal antibody MOv18, directed against the {alpha}-isoform of folate receptor (FR), was investigated to identify the optimal radioconjugate for radioimmunotherapy of minimal residual disease in ovarian cancer. Methods: Pharmacokinetics, biodistribution, long-term therapeutic efficacy and toxicity of MOv18, labeled with the beta-emitters {sup 131}I, {sup 90}Y and {sup 177}Lu, were compared in a xenografted mouse model, composed by two cell lines, A431FR and A431MK, differing only for FR expression. Results: A shorter blood clearance and a higher tumor uptake were observed for {sup 90}Y- and {sup 177}Lu- compared to {sup 131}I-MOv18, and a shorter blood pharmacokinetics was recorded in A431FR-bearing animals. At equitoxic maximum tolerable doses, the general irradiation by {sup 131}I- and {sup 90}Y-MOv18 gives rise to strong targeted effects on A431FR and nontargeted effects on A431MK tumors, while {sup 177}Lu-MOv18 was able to eradicate small size tumor masses expressing the antigen of interest exerting only mild non-targeted effects. Conclusion: {sup 177}Lu-MOv18 at the maximal tolerated dose is the immunoradioconjugate with the best therapeutic window in experimental conditions of small tumor volume.

Stability of /sup 131/I--thyroxine and of /sup 131/I-tri-iodothyronine: the influence of radiolytic disintegration on certain diagnostic tests

Energy Technology Data Exchange (ETDEWEB)

Reviczky, A.L.; Szanto, L.

1974-01-01

The blood-protein fractions responsible for the transport of thyroid hormones (TBG, TBPA, TBA) were assayed for their thyroxine-binding capacity in the serum of the same control subject over a one-year period, by a procedure based on the isotope-dilution technique. In the dilutions of /sup 131/I--T/sub 4/ (Amersham RCC) required for the procedure, the ratio /sup 131/I--T/sub 4/:/sup 131/I--T/sub 3/ was measured in every case. Parallel with the accumulation of /sup 131/I--T/sub 3/ resulting from deiodination of /sup 131/I--T/sub 4/, the binding capacity of the individual fractions was found to have shifted from TBG to TBPA. The fact that, in contrast to the principle of the isotope-dilution technique, the labelled substance and the non-radioactive T/sub 4/ were partly different, suggests that the measurements of radioactivity do not reflect the true binding conditions of T/sub 4/. Successive batches of /sup 131/I--T/sub 3/ were examined in the same manner, and the values of the Hamolsky test were determined in the same serum. The figures displayed little variations and /sup 131/I--T/sub 3/ was also found significantly more stable than /sup 131/I--T/sub 4/. Thus, the Hamolsky test was found to represent a fairly reliable indicator of thyroid function, in contrast to measurement of the T/sub 4/-binding capacity of the blood protein fractions by the isotope-dilution technique, the results of which are uncertain and therefore inconclusive in both clinical and therapeutic respects. It is suggested that the /sup 131/I--T/sub 4/ serving for the assays should be supplied as a substance and diluted before use, but not later than a few days after preparation. The advantages of doublet tagging are pointed out.

Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant

International Nuclear Information System (INIS)

Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos

2011-01-01

It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO 3 H and 137 Cs, not generating either monetary or environmental cost associated to the estimation. The 137 Cs was determined by gamma spectrometry and the 3 H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of 3 H and 137 Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the 3 H and 6.2 and 13.9 for the 137 Cs. The ratio of dilution factors of calculated 3 H and 137 Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

Support housing for radioisotope generation

International Nuclear Information System (INIS)

Fries, B.A.

1976-01-01

A support housing for on-site radioisotope generation is disclosed in which the formation of a short-lived daughter radioisotope from its longer-lived parent features countercurrent batch flow of the eluting reagent interior of the housing. 6 claims, 4 drawing figures

Homogeneous aqueous solution nuclear reactors for the production of Mo-99 and other short lived radioisotopes

International Nuclear Information System (INIS)

2008-09-01

Technetium-99m ( 99m Tc), the daughter of Molybdenum-99 ( 99 Mo), is the most commonly used medical radioisotope in the world. It accounts for over twenty-five million medical procedures each year worldwide, comprising about 80% of all radiopharmaceutical procedures. 99 Mo is mostly prepared by the fission of uranium-235 targets in a nuclear reactor with a fission yield of about 6.1%. Currently over 95% of the fission product 99 Mo is obtained using highly enriched uranium (HEU) targets. Smaller scale producers use low enriched uranium (LEU) targets. Small quantities of 99 Mo are also produced by neutron activation through the use of the (n, γ) reaction. The concept of a compact homogeneous aqueous reactor fuelled by a uranium salt solution with off-line separation of radioisotopes of interest ( 99 Mo, 131 I) from aliquots of irradiated fuel solution has been cited in a few presentations in the series of International Conference on Isotopes (ICI) held in Vancouver (2000), Cape Town (2003) and Brussels (2005) and recently some corporate interest has also been noticeable. Calculations and some experimental research have shown that the use of aqueous homogeneous reactors (AHRs) could be an efficient technology for fission radioisotope production, having some prospective advantages compared with traditional technology based on the use of solid uranium targets irradiated in research reactors. This review of AHR status and prospects by a team of experts engaged in the field of homogeneous reactors and radioisotope producers yields an objective evaluation of the technological challenges and other relevant implications. The meeting to develop this report facilitated the exchange of information on the 'state of the art' of the technology related to homogeneous aqueous solution nuclear reactors, especially in connection with the production of radioisotopes. This publication presents a summary of discussions of a consultants meeting which is followed by the technical

List of ERDA radioisotope (customers with summary of radioisotope shipments FY 1975

International Nuclear Information System (INIS)

Simmons, J.L.; Gano, S.R.

1976-01-01

The twelfth edition of the ERDA radioisotope customer list has been prepared at the request of the Division of Biomedical and Environmental Research. The purpose of this document is to list the FY 1975 commercial radioisotope production and distribution activities of USERDA facilities at Argonne National Laboratory, Battelle, Pacific Northwest Laboratories, Brookhaven National Laboratory, United Nuclear Inc., Idaho Operations Office, Hanford Engineering Development Laboratory, Mound Laboratory, Oak Ridge National Laboratory, and Savannah River Plant

Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant; Estimativa do fator de diluicao para efluentes radioativos liquidos empregando os radiotracadores H-3 e Cs-137 presentes como poluentes

Energy Technology Data Exchange (ETDEWEB)

Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos, E-mail: mbnisti@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO {sup 3}H and {sup 137}Cs, not generating either monetary or environmental cost associated to the estimation. The {sup 137}Cs was determined by gamma spectrometry and the {sup 3}H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of {sup 3}H and {sup 137}Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the {sup 3}H and 6.2 and 13.9 for the {sup 137}Cs. The ratio of dilution factors of calculated {sup 3}H and {sup 137}Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

Inorganic, radioisotopic and organic analysis of 241-AP-101 tank waste

International Nuclear Information System (INIS)

SK Fiskum; PR Bredt; JA Campbell; LR Greenwood; OT Farmer; GJ Lumetta; GM Mong; RT Ratner; CZ Soderquist; RG Swoboda; MW Urie; JJ Wagner

2000-01-01

Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids. The characterization of the 241-AP-101 composite samples included: (1) Inductively-coupled plasma spectrometry for Ag, Al, Ba, Bi, Ca, Cd, Cr, Cu, Fe, K, La, Mg, Mn, Na, Nd, Ni, P, Pb, Pd, Ru, Rh, Si, Sr, Ti, U, Zn, and Zr (Note: Although not specified in the test plan, As, B, Be, Co, Li, Mo, Sb, Se, Sn, Tl, V, W, and Y were also measured and reported for information only) (2) Radioisotopic analyses for total alpha and total beta activities, 3 H, 14 C, 60 Co, 79 Se, 90 Sr, 99 Tc as pertechnetate, 106 Ru/Rh, 125 Sb, 134 Cs, 137 Cs, 152 Eu, 154 Eu, 155 Eu, 238 Pu, 239+240 Pu, 241 Am, 242 Cm, and 243+244 Cm; (3) Inductively-coupled plasma mass spectrometry for 237 Np, 239 Pu, 240 Pu, 99 Tc, 126 Sn, 129 I, 231 Pa, 233 U, 234 U, 235 U, 236 U, 238 U, 241 AMU, 242 AMU, 243 AMU, As, B, Be, Ce, Co, Cs, Eu, I, Li, Mo, Pr, Rb, Sb, Se, Ta, Te, Th, Tl, V, and W; (4) total U by kinetic phosphorescence analysis; (5) Ion chromatography for Cl, F, NO 2 , NO 3 , PO 4 , SO 4 , acetate, formate, oxalate, and citrate; (6) Density, inorganic carbon and organic carbon by two different methods, mercury, free hydroxide, ammonia, and cyanide. The 241-AP-101 composite met all contract limits (molar ratio of analyte to sodium or ratio of becquerels of analyte to moles of sodium) defined in Specification 7 for Envelope A. Except for a few cases, the

Thiamazole Pretreatment Lowers the (131)I Activity Needed to Cure Hyperthyroidism in Patients With Nodular Goiter.

Science.gov (United States)

Kyrilli, Aglaia; Tang, Bich-Ngoc-Thanh; Huyge, Valérie; Blocklet, Didier; Goldman, Serge; Corvilain, Bernard; Moreno-Reyes, Rodrigo

2015-06-01

Relatively low radioiodine uptake (RAIU) represents a common obstacle for radioiodine ((131)I) therapy in patients with multinodular goiter complicated by hyperthyroidism. To evaluate whether thiamazole (MTZ) pretreatment can increase (131)I therapeutic efficacy. Twenty-two patients with multinodular goiter, subclinical hyperthyroidism, and RAIU effective option than LID.

Radioisotope conveyor ash meter

International Nuclear Information System (INIS)

Savelov, V.D.

1994-01-01

Radioisotope conveyor ash meter realizes persistent measuring of ashiness of coal and products of its enrichment on the belt conveyor without contact. The principle of ash meter acting is based on functional dependence of the gamma radiation flows backscattering intensity of radioisotope sources from the ash volume content in the controlled fuel. Facility consists from the ashiness transducer and the processing and control device

Modular Stirling Radioisotope Generator

Science.gov (United States)

Schmitz, Paul C.; Mason, Lee S.; Schifer, Nicholas A.

2016-01-01

High-efficiency radioisotope power generators will play an important role in future NASA space exploration missions. Stirling Radioisotope Generators (SRGs) have been identified as a candidate generator technology capable of providing mission designers with an efficient, high-specific-power electrical generator. SRGs high conversion efficiency has the potential to extend the limited Pu-238 supply when compared with current Radioisotope Thermoelectric Generators (RTGs). Due to budgetary constraints, the Advanced Stirling Radioisotope Generator (ASRG) was canceled in the fall of 2013. Over the past year a joint study by NASA and the Department of Energy (DOE) called the Nuclear Power Assessment Study (NPAS) recommended that Stirling technologies continue to be explored. During the mission studies of the NPAS, spare SRGs were sometimes required to meet mission power system reliability requirements. This led to an additional mass penalty and increased isotope consumption levied on certain SRG-based missions. In an attempt to remove the spare power system, a new generator architecture is considered, which could increase the reliability of a Stirling generator and provide a more fault-tolerant power system. This new generator called the Modular Stirling Radioisotope Generator (MSRG) employs multiple parallel Stirling convertor/controller strings, all of which share the heat from the General Purpose Heat Source (GPHS) modules. For this design, generators utilizing one to eight GPHS modules were analyzed, which provided about 50 to 450 W of direct current (DC) to the spacecraft, respectively. Four Stirling convertors are arranged around each GPHS module resulting in from 4 to 32 Stirling/controller strings. The convertors are balanced either individually or in pairs, and are radiatively coupled to the GPHS modules. Heat is rejected through the housing/radiator, which is similar in construction to the ASRG. Mass and power analysis for these systems indicate that specific

Theoretical study of the Cs isotope exchange reaction of CsI + Cs' → Cs + ICs' (Contract research)

International Nuclear Information System (INIS)

Kobayashi, Takanori; Hashimoto, Masashi; Yokoyama, Keiichi

2015-12-01

To discuss the exchange reaction of Cs isotope by CsI + Cs' → Cs + ICs', the structure and chemical properties of Cs 2 I intermediate and potential energy surface of the entrance reaction are calculated using M06/def2-TZVPPD density functional calculation. The calculation shows that the reaction to the intermediate has no barrier and the two Cs-I bonds of Cs 2 I are chemically equivalent. These results suggest that the rate of the Cs exchange reaction of CsI + Cs' → Cs + ICs' is as high as the collision rate. (author)

IPENS's social role in scientific and technological development of radioisotope and radiopharmaceutical production - (1950 -1980)

International Nuclear Information System (INIS)

Gordon, Ana Maria P.L.

2009-01-01

Some facts and figures are present in the existent interaction between the Instituto de Pesquisas Energeticas e Nucleares (IPEN) and the medical community. Among other characteristics, the IPEN has a permanent seat in the Biology and Nuclear Medicine Society and, the present Radiopharmacy Center, has had the continuous concern, since the Instituto de Energia Atomica (IEA) creation until today (2009), to perform an excellent approach with the medical faculty. In the past, some physicians would complete their courses in Europe and in the United States of America, and there noticed the importance of radioisotopes applications in medicine, mainly, in the beginning of these activities, with the I-131. Returning to Brazil, they requested that the former IEA, today IPEN researchers used the research reactor IEA-R1, installed in Sao Paulo, at Universidade Sao Paulo (USP) campus, for radioisotopes production. Then, in the late 1959, the first production line from the I-131 took place. The IPEN starts to accomplish what was planned as one of its targets, at the act of its official creation on August 31, 1956. From 1961 on, there was a continuous flux of I-131 and other radiopharmaceuticals production. The recovery and analysis of these happenings, in the Brazilian society cultural historic context, were partially published in different previous works. Nevertheless, history is dynamic and gains new interpretations, in the present research, from the reading of novel research sources, both primary and secondary, not explores so far - reports, interviews with IPEN researchers and papers published or divulged in meetings, either scientific or bureaucratic. This research is part of project supported by the Fundacao de Amparo a Pesquisa do Estado de Sao Paulo (FAPESP), with the aim, among others, of contributing for the analysis of the transformations occurred in all of the IPEN research lines, plus the social role of this institution for science and technology development. The

Operational tests and irradiation programming proposal for the industrial production of {sup 131} I in the TRIGA Mark III reactor of the Nuclear Centre (ININ); Pruebas operacionales y propuesta de programacion de irradiacion para la produccion industrial de {sup 131} I en el reactor TRIGA Mark III del Centro Nuclear (ININ)

Energy Technology Data Exchange (ETDEWEB)

Alanis M, J.; Reyes J, J.L.; Ruiz C, M.A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2003-07-01

In the National Institute of Nuclear Research it was recently finished the project for the production of I-131 at industrial level, the one which can divide basically in: (a) Preparation of the raw materials (TeO{sub 2}), (b) Sintering, (c) Neutron irradiation and (d) Separation of the I-131. With the end of starting the industrial production of this process, in this work it is presented the operational tests and an irradiation proposal of the TeO{sub 2} to obtain quantities of I-131 that cover, if not totally, partially the national market. For this, they were carried out irradiation tests of 6 samples to different flows of neutrons. The result of these tests settles down that irradiating a mass of 240 g TeO{sub 2} to a neutron flow of 6.53 x 10{sup 12} n/cm{sup 2}s in 4 cycles of 30 h per week approximately 2.54 Ci/week of I-131 distilled are obtained, which represents 35% of the demand of the Plant of Radioisotopes production of the ININ. (Author)

Radiological and physiological studies on the role of some therapeutic agents used for internal decontamination of radionuclides from male albino rats

International Nuclear Information System (INIS)

Mangood, S.A.

2008-01-01

With the earths increasing nuclear arsenal and the growing use of nuclear energy, the possibility of radiological accidents involving release of radioactive materials, internal contamination may consequently occurs via inhalation, ingestion or absorption of radioisotopes.Therefore, the present work was oriented to deal with four topics related to the internal decontamination of two of the most widely used isotopes, namely 134 Cs and 60 Co from contaminated rats:-In vitro study aimed to select agents that can strongly bind the two metal ions and elucidate the best conditions and the factors affecting this binding. The tested agents were bentonite, vermiculite and Prussian blue (PB). The sorption capacity of PB and vermiculite for both metal ions was high and equivalent to more than 10 11 Bq 137 Cs or 60 Co per gram sorbent. As bentonite has lower capacity to both isotopes, further in vivo experiments were performed with PB and vermiculite.-In vivo studies, via 5 groups of rats, devoted to investigate the kinetics of excretion of 134 Cs and/or 60 Co from contaminated rats. The biological half lives of excretion, excretion stages for both isotopes and the effect of route of entry on the excretion were estimated.-In vivo studies aimed to investigate the effectiveness of PB + vermiculite and CaDTPA as therapeutic agents for accelerating the elimination of 134 Cs and/or 60 Co from contaminated rats. The study was performed via 6 groups of rats given different regimes of therapy. The results showed the high efficiency of PB + vermiculite for accelerating elimination of 134 Cs and orally administrated 60 Co while CaDTPA succeeded in accelerating intraperitoneally administrated 60 Co. The study proved that oral administration of PB + vermiculite and injection with CaDTPA at the same time is very effective in accelerating elimination of both contaminants simultaneously.-The physiological studies aimed to evaluate the hazardous effects of 134 Cs and/or 60 Co incorporation and

Pu Radioisotopes and 241Am as Alternative Chronostratigraphic Markers in Tropical Regions: An Application in Havana Bay (Cuba)

International Nuclear Information System (INIS)

Alvarado, J.A. Corcho; Froidevaux, P.; Bochud, F.; Diaz-Asencio, M.; Hernandez, C.M. Alonso; Sanchez-Cabeza, J.A.

2011-01-01

The low 137 Cs activity observed in marine sediments of tropical regions often precludes its use as chronostratigraphic marker. Here we present a study on the use of Pu and Am radioisotopes as alternative markers to constrain the 210 Pb ages in a sediment core of the Havana Bay (Cuba). Mean activity ratios of 238 Pu/ 239,240 Pu, 241 Am/ 239,240 Pu and 241 Pu/ 239 , 240 Pu indicated that the nuclear weapon tests (NWT) fallout is the main source of the anthropogenic radionuclides. While the inventory of 137 Cs in the sediments is lower than the expected fallout inventory, 239,240 Pu accumulates in the sediments with inventories higher than the expected fallout inventory. The high fluxes of 239,240 Pu are nevertheless corroborated here through use of 210 Pb, and confirm that focusing of solid particles is of great importance in the investigated site. 239,240 Pu showed to be a useful time tracer in marine sites where the 137 Cs signal is very low. (author)

The efficient importation and distribution of radioisotopes. Suggestions for the most economic importation of radioisotopes

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-08-01

In the course of their work in many Member States, IAEA technical assistance experts have sometimes encountered difficulties in connection with the importation of radioactive isotopes. In some countries they have been consulted as to the possible improvement of import procedures. The purpose of this publication is to summarize the experience that has been gained in the hope that it may be useful both to scientists who wish to import radioisotopes for their work and to public officials who are concerned with the administrative and financial aspects of the problem. This question is of considerable importance because many countries have only limited resources of scientific man-power and foreign exchange and hence it is essential, if these resources are to be utilized fully, that efficient importing procedures be established. Furthermore, the success or failure of technical assistance activities may depend on whether radioisotopes needed for the project can be efficiently imported. Although the data summarized in this publication are based mainly on the experience of medical users of radioisotopes, they are equally applicable to their uses in other fields such as agriculture and hydrology. This publication covers the subject of importation and distribution of radioisotopes, and concludes with a brief section on the domestic production of short-lived radioisotopes in research reactors.

The efficient importation and distribution of radioisotopes. Suggestions for the most economic importation of radioisotopes

International Nuclear Information System (INIS)

1963-01-01

In the course of their work in many Member States, IAEA technical assistance experts have sometimes encountered difficulties in connection with the importation of radioactive isotopes. In some countries they have been consulted as to the possible improvement of import procedures. The purpose of this publication is to summarize the experience that has been gained in the hope that it may be useful both to scientists who wish to import radioisotopes for their work and to public officials who are concerned with the administrative and financial aspects of the problem. This question is of considerable importance because many countries have only limited resources of scientific man-power and foreign exchange and hence it is essential, if these resources are to be utilized fully, that efficient importing procedures be established. Furthermore, the success or failure of technical assistance activities may depend on whether radioisotopes needed for the project can be efficiently imported. Although the data summarized in this publication are based mainly on the experience of medical users of radioisotopes, they are equally applicable to their uses in other fields such as agriculture and hydrology. This publication covers the subject of importation and distribution of radioisotopes, and concludes with a brief section on the domestic production of short-lived radioisotopes in research reactors

Differential expression profiling of circulation microRNAs in PTC patients with non-131I and 131I-avid lungs metastases: a pilot study

International Nuclear Information System (INIS)

Qiu, Zhong-Ling; Shen, Chen-Tian; Song, Hong-Jun; Wei, Wei-Jun; Luo, Quan-Yong

2015-01-01

Introduction: Loss of the ability to concentrate 131 I is one of the important causes of radioiodine-refractory disease in papillary thyroid carcinoma (PTC). Recent advantages of serum microRNAs (miRNAs) open a new realm of possibilities for noninvasive diagnosis and prognosis of many cancers. The aim of the current study was to identify differential expression profiling of circulation miRNAs in PTC patients with non- 131 I and 131 I-avid lungs metastases. Methods: The expressions of miRNAs were examined using miRNA microarray chip. The most significantly changed miRNAs from microarray were verified by using qRT-PCR. The potential miRNAs regulating target genes and their preliminary biological functions were forecasted by Bioinformatic analysis. Results: Compared to 131 I-avid lung metastases, 13 kinds of significantly differential serum miRNAs including 5 upregulated miRNAs (miR-1249, miR-106a, miR-503, miR-34c-5p, miR-1281) and 8 downregulated miRNAs (miR-1915, miR-2861, miR-3196, miR-500, miR-572, miR-33b, miR-554, miR-18a) in PTC patients with non- 131 I-avid lung metastases were identified. Bioinformatic analysis demonstrated that miR-106a was the core miRNA regulating 193 genes in the network. The results of validation confirmed the up-regulation of miR-106a in non- 131 I-avid lungs metastatic PTC patients. Conclusion: Differentially expressed serum miRNA profiles between PTC patients with non- 131 I and 131 I-avid lungs metastases were analyzed. These findings in our present study could represent new clues for the diagnostic and therapeutic strategy in PTC patients with non- 131 I-avid metastatic disease

Nano-technology contributions towards the development of high performance radioisotope generators: The future promise to meet the continuing clinical demand.

Science.gov (United States)

Sakr, Tamer M; Nawar, Mohamed F; Fasih, T W; El-Bayoumy, S; Abd El-Rehim, H A

2017-11-01

Nanostructured materials attracted considerable attention because of its high surface area to volume ratio resulting from their nano-scale dimensions. This class of sorbents is expected to have a potential impact on enhancement the efficacy of radioisotope generators for diagnostic and therapeutic applications in nuclear medicine. This review provides a summary on the importance of nanostructured materials as effective sorbents for the development of clinical-scale radioisotope generators and outlining the assessment of recent developments, key challenges and promising access to the near future. Copyright © 2017 Elsevier Ltd. All rights reserved.

Evaluation of internal occupational exposure of workers from nuclear medicine services by aerosol analysis containing 131I

International Nuclear Information System (INIS)

Carneiro, Luana Gomes; Sampaio, Camilla da Silva; Dantas, Ana Leticia Almeida; Lucena, Eder Augusto; Santos, Maristela Souza; Dantas, Bernardo Maranhao; Paula, Gustavo Affonso de

2014-01-01

This study evaluated the risk of internal occupational exposure associated with the incorporation of 131 I via inhalation, in Nuclear Medicine Services, using aerosol analysis techniques. Occupationally Exposed Individuals (IOE) involved in handling this radionuclide are subject to chronic exposure, which can lead to an increase in the committed effective dose. Results obtained in preliminary studies indicate the occurrence of incorporation of 131 I by workers involved in handling solutions for radioiodine therapy procedures. The evaluation was carried out in radiopharmacy lab (nuclear medicine service) of a public hospital located in the city of Rio de Janeiro. After confirmed the presence of the radioisotope, by a qualitative assessment, it was determined an experimental arrangement for sample collection and were detected and quantitated the presence of steam 131 I during routine work. The average concentration of activity obtained in this study was 3 Bq / m 3 . This value is below of Derived Concentration in Air (DCA) of 8.4 x 10 3 Bq of 131 I / m 3 corresponding to a committed effective dose of 1.76 x 10 -4 mSv. These results demonstrate that the studied area is safe in terms of internal exposure of workers. However, the presence of 131 I should be periodically reevaluated, since this type of exposure contributes to the increase of the individual effective doses. Based on the data obtained improvements were suggested in the exhaust system and the use of good work practices in order to optimize the exposures

Biological dosimetry in patients with differenced thyroid carcinoma treated with Iodine-131

International Nuclear Information System (INIS)

Vallerga, M.; Taja, Maria R.; Radl, A.; Rojo, Ana M.; Deluca, G.; Di Giogio, Marina; Fadel, A.; Chebel, G.; Oneto, A.; Cabrejas, Mariana

2007-01-01

The differentiated thyroid carcinoma (DTC), constitutes the 90 % of the thyroid gland cancers. 80% of patients are cured after the initial therapy and 12% remained disease-free after successive treatments. The 24 patients included in this study represent a sample of the aforementioned 12% and 8%, with recurrence in the first decade post-treatment (local disease and/or recurrence at distance). The internal radiotherapy with 131 I in patients with DTC is used within the therapeutic schema as a step post-thyroidectomy. The success of the therapy is to get a lethal dose in the tumor tissue, which depends on the therapeutic activity and the retention of 131 I, without exceeding the dose of tolerance in healthy tissues. The most widespread way of administration is the empirical prescription which considers the clinical and laboratory parameters for its determination. In this work, the treatment protocol applied incorporates assessment by biological (DB) and internal (DI) dosimetry for estimating absorbed dose to the whole body and bone marrow to manage a personalized therapeutic dose for each patient. The biological dose estimation is based on the quantification of chromosomal aberrations, which is often referred to a dose-response curve in which lymphocytes are irradiated in vitro with 131 I, allowing to determine the dose in vivo of circulating lymphocytes patients [es

An experiment to use medical I-131 as tracer in a city sewer system

Energy Technology Data Exchange (ETDEWEB)

Ulbrich, Susanne; Fischer, Helmut W. [University of Bremen, Institute of Environmental Physics, Otto-Hahn-Allee 1, D-28359 Bremen (Germany)

2014-07-01

City sewer systems have to reliably carry residential and industrial wastewater to treatment plants, often mixed with rainwater. Transport in the sewer system is regularly modelled in order to predict sewerage levels, transport velocities and volume discharges. Radioisotopes would be interesting tracers, as they can be detected quickly and without the need of applying wet chemistry. Medical isotopes are released in large quantities (many MBq) by excretion from patients either at the location of administration or from elsewhere, most probably the patient's home. Depending on diagnostic or treatment modality, isotopes of different physical characteristics are used, often bound to compounds of specific metabolic behaviour. Routine environmental surveillance regularly detects the most common diagnostic ({sup 99m}Tc) and therapeutic ({sup 131}I) isotopes in city wastewater samples. Except for {sup 131}I in the case of a nuclear emergency, no contributions from sources other than medical are expected. Medical isotopes therefore might be used for tracing purposes, provided individual inputs can be identified and separated. A field experiment has been designed involving {sup 131}I releases from a single patient who had undergone radioiodine thyroid ablation therapy. This modality is applied after thyroid cancer surgery in order to destroy residual thyroid tissue. Activities up to 5 GBq of {sup 131}I are used which are excreted within few days, as no iodine-retaining thyroid tissue remains. In Germany, about 20,000 of these treatments are performed yearly. For a sewer system of 500,000 inhabitants, about 150 cases would be expected per year, making it quite improbable to have interference between individual patient releases in the same region of the city sewer system. Practically, the radiometric laboratory was informed of the expected release of an (anonymous) patient from the collaborating radiotherapy unit several days in advance, plus the approximate location of

Notification determining details of technical standards concerning transport of radioisotopes or goods contaminated by radioisotopes outside works or enterprises

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the regulation for the execution of the law on the prevention of radiation injuries by radioisotopes. Terms are used in this rule for the same meanings as in the regulation. The concentration of radioisotopes to which the technical standards for transport outside enterprises are not applied is 0.002 micro-curie per gram. The radioisotopes which can be transported as L type transported goods are defined in detail, excluding explosive or spontaneously igniting radioisotopes. The quantity limit of radioisotopes which can be transported as A type transported goods is the values A 1 and A 2 defined in this rule. The permissible surface density defined by the Director General of the Science and Technology Agency are 1/100,000 micro-curie per cm 2 for the radioisotopes emitting alpha-ray, and 1/10,000 micro-curie per cm 2 for the radioisotopes which do not emit alpha-ray. The leak quantity of radioisotopes specified by the Director General is 1/1,000,000 of A 2 value for BM type transported goods and 1/1,000 of A 2 value for BU type goods. The test conditions for each type of transported goods, dangerous goods, the limit of the number of transported goods and signs are stipulated, respectively. Permissible exposure dose is 1.5 rem a year for persons other than radiation workers. (Okada, K.)

IEA-R1 Nuclear Research Reactor: 58 Years of Operating Experience and Utilization for Research, Teaching and Radioisotopes Production

Energy Technology Data Exchange (ETDEWEB)

Cardenas, Jose Patricio Nahuel; Filho, Tufic Madi; Saxena, Rajendra; Filho, Walter Ricci [Nuclear and Energy Research Institute, IPEN-CNEN/SP, Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242 Cid Universitaria CEP: 05508-000- Sao Paulo-SP (Brazil)

2015-07-01

IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (Nuclear and Energy Research Institute) IPEN, Sao Paulo, Brazil is the largest power research reactor in Brazil, with a maximum power rating of 5 MWth. It is being used for basic and applied research in the nuclear and neutron related sciences, for the production of radioisotopes for medical and industrial applications, and for providing services of neutron activation analysis, real time neutron radiography, and neutron transmutation doping of silicon. IEA-R1 is a swimming pool reactor, with light water as the coolant and moderator, and graphite and beryllium as reflectors. The reactor was commissioned on September 16, 1957 and achieved its first criticality. It is currently operating at 4.5 MWth with a 60-hour cycle per week. In the early sixties, IPEN produced {sup 131}I, {sup 32}P, {sup 198}Au, {sup 24}Na, {sup 35}S, {sup 51}Cr and labeled compounds for medical use. During the past several years, a concerted effort has been made in order to upgrade the reactor power to 5 MWth through refurbishment and modernization programs. One of the reasons for this decision was to produce {sup 99}Mo at IPEN. The reactor cycle will be gradually increased to 120 hours per week continuous operation. It is anticipated that these programs will assure the safe and sustainable operation of the IEA-R1 reactor for several more years, to produce important primary radioisotopes {sup 99}Mo, {sup 125}I, {sup 131}I, {sup 153}Sm and {sup 192}Ir. Currently, all aspects of dealing with fuel element fabrication, fuel transportation, isotope processing, and spent fuel storage are handled by IPEN at the site. The reactor modernization program is slated for completion by 2015. This paper describes 58 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. (authors)

CsPbBr3 nanocrystal saturable absorber for mode-locking ytterbium fiber laser

Science.gov (United States)

Zhou, Yan; Hu, Zhiping; Li, Yue; Xu, Jianqiu; Tang, Xiaosheng; Tang, Yulong

2016-06-01

Cesium lead halide perovskite nanocrystals (CsPbX3, X = Cl, Br, I) have been reported as efficient light-harvesting and light-emitting semiconductor materials, but their nonlinear optical properties have been seldom touched upon. In this paper, we prepare layered CsPbBr3 nanocrystal films and characterize their physical properties. Broadband linear absorption from ˜0.8 to over 2.2 μm and nonlinear optical absorption at the 1-μm wavelength region are measured. The CsPbBr3 saturable absorber (SA), manufactured by drop-casting of colloidal CsPbBr3 liquid solution on a gold mirror, shows modulation depth and saturation intensity of 13.1% and 10.7 MW/cm2, respectively. With this SA, mode-locking operation of a polarization-maintained ytterbium fiber laser produces single pulses with duration of ˜216 ps, maximum average output power of 10.5 mW, and the laser spectrum is centered at ˜1076 nm. This work shows that CsPbBr3 films can be efficient SA candidates for fiber lasers and also have great potential to become broadband linear and nonlinear optical materials for photonics and optoelectronics.

Design and simulation of an automation system of a production process and fractionation of {sup 131}I, using strategies of advanced control; Diseno y simulacion de un sistema de automatizacion del proceso de produccion y fraccionamiento de {sup 131}I, utilizando estrategias de control avanzado

Energy Technology Data Exchange (ETDEWEB)

Paez, Jose; Arias, Pablo; Miranda, Jesus, E-mail: jpaez@jpen.gob.pe, E-mail: parias@ipen.gob.pe, E-mail: jmiranda@ipen.gob.pe [Instituto Peruano de Energia Nuclear (lPEN), Lima (Peru). Direccion de Servicios. Division de Instrumentacion Nuclear

2013-10-01

In this report, the results are obtained in the design and simulation of a control system using advanced strategies in a production cell in the Plant Production of Radioisotopes of IPEN. The results demonstrate that the temperature of the coalition oven is stabilized after 30 minutes, being constituted in an advantage to obtain the maximum yield of the cell production of {sup 131}I; also, an integral good controller has been designed that allows to obtain a mathematical model that reproduces with enough accuracy the behavior of the process. With the final simulation it has been to demonstrate that the System Control of Temperature of the Cell Production of {sup 131}I is a controllable system and allows to carry out the respective sequence with other variables of control of the production cell. (author)

Medical Radioisotopes Production Without A Nuclear Reactor

Energy Technology Data Exchange (ETDEWEB)

Van der Keur, H.

2010-05-15

This report is answering the key question: Is it possible to ban the use of research reactors for the production of medical radioisotopes? Chapter 2 offers a summarized overview on the history of nuclear medicine. Chapter 3 gives an overview of the basic principles and understandings of nuclear medicine. The production of radioisotopes and its use in radiopharmaceuticals as a tracer for imaging particular parts of the inside of the human body (diagnosis) or as an agent in radiotherapy. Chapter 4 lists the use of popular medical radioisotopes used in nuclear imaging techniques and radiotherapy. Chapter 5 analyses reactor-based radioisotopes that can be produced by particle accelerators on commercial scale, other alternatives and the advantages of the cyclotron. Chapter 6 gives an overview of recent developments and prospects in worldwide radioisotopes production. Chapter 7 presents discussion, conclusions and recommendations, and is answering the abovementioned key question of this report: Is it possible to ban the use of a nuclear reactor for the production of radiopharmaceuticals? Is a safe and secure production of radioisotopes possible?.

Meta[{sup 131}I]iodobenzylguanidine therapy for patients with metastatic and unresectable pheochromocytoma and paraganglioma

Energy Technology Data Exchange (ETDEWEB)

Goldsby, Robert E. [Division of Pediatric Oncology, Department of Pediatrics, University of California, San Francisco, CA 94143-0106 (United States); Fitzgerald, Paul A. [Division of Endocrinology, Department of Medicine, University of California, San Francisco, CA 94143-1222 (United States)], E-mail: paul.fitzgerald@ucsf.edu

2008-08-15

Introduction: Pheochromocytomas (PHEOs) and paragangliomas (PGLs) are tumors that can exhibit a malignant behavior. Targeted radiotherapy with {sup 131}I-metaiodobenzylguanidine ({sup 131}I-MIBG) has proven useful in patients with unresectable, metastatic and/or relapsed disease. Methods: We review the literature and our experience at UCSF to highlight important characteristics of PHEO/PGL and the use of {sup 131}I-MIBG in the treatment of this disease. Results: These tumors are rare, with a diagnosed incidence of only two to four cases per million annually; 40% are discovered at autopsy. Clinical manifestations are caused by excess secretion of catecholamines, although some PGLs are nonsecretory. Approximately 25% of patients with PHEO/PGLs have an underlying genetic predisposition. The risk of a germline mutation is higher in children. Diagnostic evaluation should include serial determinations of fractionated metanephrines and serum chromogranin A. Staging requires both {sup 123}I-MIBG and full-body magnetic resonance imaging or {sup 18}FDG-PET scanning. The primary treatment for PHEO/PGL is resection. Patients may be candidates for treatment with {sup 131}I-MIBG if they have unresectable or metastatic tumors that are avid for MIBG. Such patients usually respond to this targeted radioisotope therapy and many achieve a durable remission. Myelosuppression is a dose-related side effect that can be treated with transfusions or autologous hematopoietic stem cells. Late side effects can include infertility, myelodysplasia and second cancers. Conclusions: Treatment with {sup 131}I-MIBG can be considered for patients if surgery is not feasible. There are significant risks associated with this treatment, but the majority of patients will respond. Treatment with {sup 131}I-MIBG should be done at institutions with experience in delivering targeted radiotherapeutics.

List of ERDA radioisotope customers with summary of radioisotope shipments, FY 1976

International Nuclear Information System (INIS)

Simmons, J.L.

1977-03-01

The thirteenth edition of the ERDA radioisotope customer list has been prepared at the request of the Office of Program Coordination, Office of the Assistant Administrator. The purpose of the document is to list the FY 1976 commercial radioisotope production and distribution activities of ERDA facilities at Argonne National Laboratory, Battelle, Pacific Northwest Laboratories, Brookhaven National Laboratory, Hanford Engineering Development Laboratory, Idaho Operations Office, Los Alamos Scientific Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Savannah River Laboratory, and United Nuclear Industries, Inc

Evolution of {sup 137}Cs and {sup 90}Sr content of the main foodstuff in Bucharest area after the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Toader, M; Vasilache, R A [Institute of Hygiene and Public Health, Bucharest (Romania)

1997-09-01

Soon after the Chernobyl accident, the radioactive cloud, carrying the nuclides released into the atmosphere, reached Romania and, due to the rainy weather, an important fallout occurred over the Romanian territory. The most important contaminants for Romania were I{sup 131}, Cs{sup 134}, Cs{sup 137} and Sr{sup 90}. As in many other countries, in the first days, I{sup 131} had the main contribution to the irradiation dose released to the population. After its decay, and the decay of other short-lived radionuclides, Cs{sup 137} and Sr{sup 90} remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. To assess the radioactive burden of foods, a long term, large scale survey was initiated at the National Institute of Hygiene and Public Health (INISP). These results were then used to assess the doses committed to cesium and strontium intake and the excedentary cancer risk for the population from Bucharest area. 5 refs, 8 figs.

The safe handling of radioisotopes

Energy Technology Data Exchange (ETDEWEB)

NONE

1964-12-31

A narrative account of a minor contamination accident in a laboratory is used to demonstrate the important role of radiation protection measures in radioisotope work and the necessity of giving proper regard to such measures. It is primarily directed towards the research scientists and medical workers using radioisotopes on a relatively small scale

Microdose study of a P-glycoprotein substrate, fexofenadine, using a non-radioisotope-labelled drug and LC/MS/MS.

Science.gov (United States)

Yamazaki, A; Kumagai, Y; Yamane, N; Tozuka, Z; Sugiyama, Y; Fujita, T; Yokota, S; Maeda, M

2010-04-01

Fexofenadine is a P-glycoprotein substrate of low bioavailability. It is primarily excreted into faeces as a parent drug via biliary excretion. The predictability from microdose data for the drug absorbed via transporters such as P-glycoprotein is not known. Therefore, this study assessed the predictability of therapeutic-dose pharmacokinetics of fexofenadine from microdosing data using non-radioisotope-labelled drug and liquid chromatography/electrospray ionization tandem mass spectrometry (LC/ESI-MS/MS). In a single dose, randomized, two-way crossover study, eight subjects received a microdose (100 microg) or a therapeutic dose (60 mg) of fexofenadine. Blood samples were collected until 12 h after dosing, and assayed using LC/MS/MS. Plasma concentration-time curves of fexofenadine between microdose and therapeutic dose were similar. The mean +/- SD of C(max) normalized to 60 mg dose after microdose and therapeutic dose were 379 +/- 147 and 275 +/- 145 ng/mL respectively. The mean AUC(last) normalized to 60 mg dose after microdose and therapeutic dose were 1914 +/- 738 and 1431 +/- 432 ng/h/mL respectively. The mean dose-adjusted C(max) and AUC(last) after microdose were higher compared with those after therapeutic dose. Individual plots of C(max) and AUC(last) normalized to 60 mg dose, were similar for microdose and therapeutic dose. None of the pharmacokinetic parameters were statistically different using anova. Overall, the microdose pharmacokinetics profile was similar to, and hence predictive of, that of the therapeutic dose. For the P-glycoprotein substrate fexofenadine, the predictability of therapeutic-dose pharmacokinetics from microdose data was good. A microdose study using a non-radioisotope-labelled drug and LC/MS/MS is convenient, and has the potential to aid the early selection of drug candidates.

NATO Allied Medical Publication 7.5 Study Draft 3 (AMedP 7.5 SD.3), NATO Planning Guide for the Estimation of CBRN Casualties

Science.gov (United States)

2015-12-01

NORTH ATLANTIC TREATY ORGANIZATION (NATO) NATO STANDARDIZATION OFFICE (NSO) NATO LETTER OF PROMULGATION [ Date ] 1. The enclosed Allied Medical...The radioisotopes modeled are 60Co, 90Sr, 99Mo, 125I, 131I, 137Cs, 192Ir, 226Ra, 238Pu, 241Am, 252Cf. 2) Whole-body irradiation (from cloudshine...Carrier 1.22 2.70 Earth Shelter 16.67 66.67 Exposed/Dismounted 1.00 1.00 Foxhole (nuclear only)† 3.00 10.00 Masonry Building 8.33 6.67 Multi-Story

Radioisotope production with a medical cyclotron

International Nuclear Information System (INIS)

Silvester, D.J.

1974-01-01

The cyclotron of Hammersmith hospital in England was completed and started the operation in 1955. The feature is in its design operable at high beam current, reaching 500μA in internal beam and 300μA in external beam. In 1960's, twelve nuclides of radioactive pharmaceuticals were produced with the cyclotron. C-11, N-13 and O-15 have been used in the form of radioactive gases such as CO or H 2 O to test lung functions. F-18 has been used for bone scanning. K-43 is employed in the research of electrolyte balancing together with Na-24 and Br-77. Fe-52 is utilized in iron ion researches as a tracer. Cs-129 is highly evaluated as an isotope for imaging cardiac clogging part. Radioisotopes must be much more used in the examination of in vivo metabolic function. For this purpose, peculiarly labelled compounds should be further developed. It is welcome that the persons paying attention to the medical prospect of cyclotrons are increasing. The author hopes to continue his endeavour to find new products made with the cyclotron for human welfare. (Wakatsuki, Y.)

Thickness measurement for the different metals by using Cs-137 gamma source with gamma transmission technique

International Nuclear Information System (INIS)

Bueyuek, B.; Tugrul, B.

2009-01-01

The purpose of this study is an experimental analysis of thickness measurement for various metals with the gamma transmission technique using Cs-137 as the radioisotope source. Lead, steel, brass, and aluminum, which are frequently used metals in industry, were chosen for the experiments. As the radioisotope source Cs-137 was preferred for the study since it has long half-life, it is mono energetic, and it penetrates the metals that were studied. Experiments were observed in the constant experimental geometry. Calibration curves for the four metal samples were plotted using the obtained results. To test the plotted calibration curves, counts for determining thickness measurement were collected for each sample and the obtained relative count values were used in conjunction with the plotted calibration curves for each sample to determine its thickness. The thicknesses of the samples have been measured with a micrometer and the results were comparatively analyzed with the measurement results obtained by the gamma transmission technique. The results of the analyses revealed that the thickness measurement values obtained with the gamma transmission technique and the thickness measurement values obtained with the conventional technique significantly converge to each other and the difference between the two values is at an acceptable level. Therefore the reliability of thickness measurements with the gamma transmission technique and the resulting calibration curves have been demonstrated.

Radioiodine 131I metabolism in human

International Nuclear Information System (INIS)

Mori, Toru

1976-01-01

Metabolic fate of orally administered 131 I in human was studied. Chronological observations of whole body radioactivity distribution and thyroid 131 I uptake curve revealed that 131 I metabolism was greatly affected by the amount of dietary iodine intake. Under the high iodine intake exceeding 1 mg per day, uptake curve showed biphasic descending type, that is, rapid accumulation during 3 to 6 hours and rapid fall up to 48 hours and gradual decrease afterwards. While, ascending type, monophasic and maximal at 24 hours, was found universary under low iodine intake less than 500 μg per day. Thyroid function should not be affected by the amount of iodine intake, and we analysed 131 I metabolism using a new four compartments which included intrathyroidal inorganic iodine pool. The results, especially hormone production rate, were found quite useful even under high iodine intake. Thyroidal organic iodine contents were calculated as approximately 2.5 mg and this value was much less than previously reported values from other countries. Administered radioiodine were mixed up with stable body iodine and reached equilibration by around 10 days. From seroimmunological, histological (microscopic and electron microscopic) studies, and irradiation studies to the cultured human thyroid cells, we concluded that this unexpected phenomenon was derived from chromosomal damage which induced gradual decrease in cell population because of inability to reproduce. Carcinogenic and genetic effects were not serious, and only three leukemic patients were reported in this country and 484 normal babies were born from 7,500 treated parents. Thus, therapeutic dose of 131 I was proved rather safe, and even when exposed to radioiodine, administration of perchlorate or thiocyanate, excessive iodine and TSH seemed effective to avoid radiation injuries. (auth.)

Clinical scale preparation and evaluation of {sup 131}I-Rituximab for Non-Hodgkin's lymphoma

Energy Technology Data Exchange (ETDEWEB)

Kameswaran, Mythili; Vimalnath, K. Viswanathan; Rajeswari, Ardhi; Joshi, Prahlad Vasudeo; Samuel, Grace [Bhabha Atomic Research Centre, Mumbai (India). Radiopharmaceuticals Div.; Sarma, H.D. [Bhabha Atomic Research Centre, Mumbai (India). Radiation Biology and Health Sciences Div.

2014-09-01

Radioimmunotherapy (RIT) with anti CD20 MoAb conjugated to a β{sup -} emitting radioisotope like {sup 131}I or {sup 90}Y has the added advantage of delivering radiation not only to tumor cells that bind the antibody but also due to a crossfire effect, to neighboring tumor cells inaccessible to the antibody. In order to make available an indigenous radioimmunotherapeutic agent for Non Hodgkin's Lymphoma (NHL), radioiodinated Rituximab has been prepared and evaluated at a clinical scale. Radioiodination of Rituximab was performed by the conventional Chloramine T method using 7.4 GBq Na{sup 131}I in a lead shielded plant. Six batches of radioiodination were prepared and characterized by electrophoresis and HPLC to evaluate the reproducibility of the product. The product remained stable retaining the radiochemical purity > 95% upto 5 days after radioiodination. In vitro cell binding studies and biodistribution studies in normal Swiss mice have indicated the potential of this molecule as a radioimmunotherapeutic agent for NHL. (orig.)

Operational tests and irradiation programming proposal for the industrial production of 131 I in the TRIGA Mark III reactor of the Nuclear Centre (ININ)

International Nuclear Information System (INIS)

Alanis M, J.; Reyes J, J.L.; Ruiz C, M.A.

2003-01-01

In the National Institute of Nuclear Research it was recently finished the project for the production of I-131 at industrial level, the one which can divide basically in: (a) Preparation of the raw materials (TeO 2 ), (b) Sintering, (c) Neutron irradiation and (d) Separation of the I-131. With the end of starting the industrial production of this process, in this work it is presented the operational tests and an irradiation proposal of the TeO 2 to obtain quantities of I-131 that cover, if not totally, partially the national market. For this, they were carried out irradiation tests of 6 samples to different flows of neutrons. The result of these tests settles down that irradiating a mass of 240 g TeO 2 to a neutron flow of 6.53 x 10 12 n/cm 2 s in 4 cycles of 30 h per week approximately 2.54 Ci/week of I-131 distilled are obtained, which represents 35% of the demand of the Plant of Radioisotopes production of the ININ. (Author)

Environmental radioactivity levels, Browns Ferry Nuclear Plant: Annual report, 1986

International Nuclear Information System (INIS)

1986-04-01

The report presents data gathered during radiological monitoring program conducted in the environs of the Browns Ferry Nuclear Plant. Dose estimates were made from concentrations of radioactivity found in samples of media including air, milk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 95% of those doses were contributed by the naturally occurring K-40 and by Sr-90 and Cs-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing. Increased levels of I-131 were reported in air, milk, and rainwater following the accident at the Chernobyl nuclear power station. In addition, Ru-103, Cs-137, and Cs-134 were identified in air particulates, and traces of Ru-103 were found in rainwater

Radiochemical studies on the separation of iodine-131 and radioiodination of some organic compounds

International Nuclear Information System (INIS)

Mohamed, M.A.I.

2010-01-01

This thesis is constituted of three chapters:Chapter I: It deals with the theoretical consideration of the subject. The chapter deals with the importance of radioisotopes in medical applications, and the physical and biological properties of these isotopes. Also, this part deals with the chemical and physical properties of both tellurium and iodine and the methods of the production of radioiodine from tellurium targets especially dry distillation method and ion exchange method. It deals with general methods of labeling, chemistry of iodine especially the most frequently used in nuclear medicine, their methods of production and applications. It includes also the techniques used for the preparation of the radioiodinated compounds, especially the electrophilic technique or the oxidative radioiodination technique. In this technique, oxidizing agents are used to oxidize iodide ions to iodonium ions capable of electrophilic attack on the aryl group of the organic compound. This chapter deals also with the receptor tracers, their types and the effects that can occur due to the binding of these receptors to the cell membrane. Since these radiopharmaceuticals are used for diagnosis and therapeutic treatment of human diseases, quality control tests such as chemical purity, radionuclidic purity, radiochemical purity, sterility, apyrogenicity and biodistribution are performed to ensure the purity, the safety and efficiency of these products for the intended nuclear medicine application.Chapter II:It contains detailed information concerning the chemicals, reagents, the radionuclides, the equipment and the counting systems used in the study. It describes production technique of iodine-131 using dry distillation method. It describes also the electrophilic radioiodination for each of Y-indole and epidepride. Analysis of the labeled products was performed using two chromatographic techniques. The first technique is thin layer chromatography in which the compound was identified by

Production of radioisotopes at the Boris Kidric Institute of Nuclear Sciences at Vinca, Yugoslavia

International Nuclear Information System (INIS)

Teofilovski, C.

1969-01-01

The investigations in order to master the production of radioisotopes were commenced simultaneously with the beginning of RA nuclear reactor construction at Vinca, in 1956. A new organization division - Laboratory for chemistry of high activity accepting beside other problems also the programme for mastering the regular production of radioactive material was formed in 1959. Various problems during the realization of this programme have been solved, starting with the staff training for work with radioactive material on the high level activity (to 7500 Ci/source), construction and equipment of the laboratory area for safe work, up to development of the whole series of chemical-technological procedures and techniques for regular production of various radioactive products, as well as the methods for their chemical, radiometric and pharmaceutical control. Owing to the successful realization of this programme, the Institute 'Boris Kidric' supplies to-day regularly 110 organizations in the country with various radioactive products, applied in medicine, industry and research. The annual product of the radioactive solutions of radioisotopes J-131, Au-198, P-32, S-35 etc., amounts to about 75 Ci, radiographic sources Ir-192 and Co-60 to 2000 Ci and Co-60 sources for teletherapy and the other applications to many thousand curies (author) [sr

Industrial radioisotope economics. Findings of the study group

International Nuclear Information System (INIS)

1965-01-01

Within twenty years of the availability of radioisotopes in quantity the use of these as tracers has been widely applied in scientific research and in industrial process and product control. Industry spends millions of dollars on these new techniques. Since the overall attitude of industry is to favour methods that involve rapid financial returns the economic benefits must be considerable. In promoting the peaceful uses of atomic energy, the IAEA is actively interested in the international exchange of experience in all applications of radioisotopes. This has been demonstrated by a number of scientific conferences where new results of direct importance to the industrial use of radioisotopes have been presented. In 1963 the IAEA also published literature survey on radioisotope applications described in the scientific literature up to 1960, classified according to industry. However, the available scientific literature was found insufficient to determine the extent of the use of radioisotopes and the economic benefits derived from it. Therefore, further fact-finding efforts were necessary. The IAEA thus decided to carry out an International Survey on the Use of Radioisotopes in Industry. In 1962 the IAEA's highly industrialized Member States Were invited to participate in the Survey; 25 declared their willingness to do so and in due course submitted their national reports. These included information on how radioisotopes were used by industry in each country and indicated the size and form of the economic advantages, primarily in terms of savings made by industry. The findings from the Survey were discussed at a Study Group Meeting on Radioisotope Economics, held in Vienna in March 1964. Forty participants from 22 countries were nominated for this Study Group. The program of the meeting was divided in three parts: (1) experience of the International Survey on the use of radioisotopes in industry; (2) present use of radioisotopes, technical and economic aspects; (3

Markets for reactor-produced non-fission radioisotopes

International Nuclear Information System (INIS)

Bennett, R.G.

1995-01-01

Current market segments for reactor produced radioisotopes are developed and reported from a review of current literature. Specific radioisotopes studied in is report are the primarily selected from those with major medical or industrial markets, or those expected to have strongly emerging markets. Relative market sizes are indicated. Special emphasis is given to those radioisotopes that are best matched to production in high flux reactors such as the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory or the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory. A general bibliography of medical and industrial radioisotope applications, trends, and historical notes is included

Research trends in radioisotopes: a scientometric analysis

International Nuclear Information System (INIS)

Sagar, Anil; Kademani, B.S.; Bhanumurthy, K.; Ramamoorthy, N.

2014-01-01

Radioisotopes or radionuclides are radioactive forms of elements and are usually produced in research reactors and accelerators. They have wide ranging applications in healthcare, industry, food and agriculture, and environmental monitoring. Following over five decades of vast experience accumulated, radioisotope technology has developed to a high degree of sophistication and it is estimated that about 200 radioisotopes are in regular use. This paper attempts to highlight the publication status and growth of radioisotope research across the world and make quantitative and qualitative assessment by way of analyzing the following features of research output based on Web of Science database during the period 1993-2012. (author)

The content of natural radioactive elements and artificial radioisotopes in Moldova's soils; Continutul unor elemente radioactive naturale si radioizotopi artificiali in solurile Moldovei

Energy Technology Data Exchange (ETDEWEB)

Stasiev, Gr. [Univ. de Stat din Moldova, Chisinau (Moldova, Republic of); Nedealcov, S.; Jigau, Gh. [Centrul Republican de Pedologie Aplicata, Chisinau (Moldova, Republic of)

2013-08-15

The results of multiyear investigations of natural radionuclide (U-238, Th-232, Ra-226, K-40) and artificial isotopes (Sr-90, Cs-137, I-131) content on soil and plants are presented. Six anomalous polluted areas were detected after Chernobyl nuclear power plant accident. (authors)

Radioisotope techniques for problem-solving on refineries

International Nuclear Information System (INIS)

Charlton, J.S.; Webb, M.

1994-01-01

Increasingly, refineries worldwide are recognizing the value of radioisotope technology in studying the operation of on-line plant. Using case studies, this paper illustrates the versatility of radioisotope techniques in a wide range of investigations: the density-profiling of distillation columns; the investigation of leaks on feed/effluent exchangers; on-line flowrate measurement; underground leakage detection. The economic benefits deriving from radioisotope applications are indicated

Pregnancy after high therapeutic doses of iodine-131 in differentiated thyroid cancer: potential risks and recommendations

International Nuclear Information System (INIS)

Casara, D.; Rubello, D.; Saladini, G.; Piotto, A.; Pelizzo, M.R.; Girelli, M.E.; Busnardo, B.

1993-01-01

Seventy female patients who had been treated with high doses of iodine-131 for differented thyroid cancer (DTC) and who had a subsequent pregnancy were evaluated. The global 131 I dose ranged from 1.85 to 16.55 GBq (mean±SD=4.39±25.20 GBq). Age at first therapy ranged from 15 to 36 years (mean±SD=24.3±5.0 years) and the interval from 131 I therapy to pregnancy varied from 2 to 10 years (mean±SD=5.3±2.8 years). The estimated radiation dose to the gonads ranged from 10 to 63 cGy (mean±SD=24.0±13.5 cGy). All patients were treated with L-thyroxine at doses capable of suppressing thyroid-stimulating hormone. Seventy-three children were followed-up and seven pregnancies are still in progress. One child was affected by Fallot's trilogy and three had a low birth weight though with subsequent regular growth; the others were healthy with subsequent regular growth. No newborn with clinical or biochemical thyroid dysfunctions was found. Two spontaneous abortions during the second month of pregnancy were recorded. One of two patients in question subsequently had two healthy children. On the basis of these data, previous administration of high 131 I doses does not appear to be a valid reason for dissuading young female DTC patients from considering pregnancy. However, patients should be advised to avoid pregnancy after 131 I administration for a period sufficient to ensure complete elimination of the radionuclide and to permit confirmation of complete disease remission, i.e. at least 1 year in our opinion. (orig.)

Evaluation of internal occupational exposure of workers from nuclear medicine services by aerosol analysis containing {sup 131}I; Avaliacao da exposicao interna de trabalhadores em servicos de medicina nuclear atraves da analise de aerossois contendo {sup 131}I

Energy Technology Data Exchange (ETDEWEB)

Carneiro, Luana Gomes; Sampaio, Camilla da Silva; Dantas, Ana Leticia Almeida; Lucena, Eder Augusto; Santos, Maristela Souza; Dantas, Bernardo Maranhao, E-mail: carneiro@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ),Rio de Janeiro, RJ (Brazil); Paula, Gustavo Affonso de [Escola SESC de Ensino Medio, Rio de Janeiro, RJ (Brazil)

2014-07-01

This study evaluated the risk of internal occupational exposure associated with the incorporation of {sup 131}I via inhalation, in Nuclear Medicine Services, using aerosol analysis techniques. Occupationally Exposed Individuals (IOE) involved in handling this radionuclide are subject to chronic exposure, which can lead to an increase in the committed effective dose. Results obtained in preliminary studies indicate the occurrence of incorporation of {sup 131}I by workers involved in handling solutions for radioiodine therapy procedures. The evaluation was carried out in radiopharmacy lab (nuclear medicine service) of a public hospital located in the city of Rio de Janeiro. After confirmed the presence of the radioisotope, by a qualitative assessment, it was determined an experimental arrangement for sample collection and were detected and quantitated the presence of steam {sup 131}I during routine work. The average concentration of activity obtained in this study was 3 Bq / m{sup 3}. This value is below of Derived Concentration in Air (DCA) of 8.4 x 10{sup 3} Bq of {sup 131}I / m{sup 3} corresponding to a committed effective dose of 1.76 x 10{sup -4} mSv. These results demonstrate that the studied area is safe in terms of internal exposure of workers. However, the presence of {sup 131}I should be periodically reevaluated, since this type of exposure contributes to the increase of the individual effective doses. Based on the data obtained improvements were suggested in the exhaust system and the use of good work practices in order to optimize the exposures.

Radioisotope applications in industry and environment: Indian scenario

International Nuclear Information System (INIS)

Pant, H.J.

2016-01-01

Applications of radioisotopes and radiation technology in industry, medicine and agriculture form an important part of India's programme of using nuclear technology for societal benefits. Radioisotope production in India started on a modest scale soon after 1 MW APSARA reactor at Trombay, Mumbai became critical in 1956. The scope of activities expanded thereafter. With the commissioning of 40 MW CIRUS reactor in 1960, the setting up of modern radioisotope processing laboratories in late sixties and the production of cobalt-60 in power reactors in megacurie quantities in late seventies made India self-sufficient in radioisotope production. The radioisotope production received a major boost in 1985 with the commissioning of high flux 100 MW DHRUVA reactor, which provided opportunity to extend the range of radioisotopes available in the country both in quantity as well in specific activity. The CIRUS reactor has been shutdown in year 2010 and 1 MW APSARA reactor is presently being upgraded to 5 MW. Today, The DHRUVA reactor operating at its full capacity is being used for production of 100 different radioisotopes those are used in industry, agriculture and medicine. (author)

Advanced Radioisotope Power Conversion Technology Research and Development

Science.gov (United States)

Wong, Wayne A.

2004-01-01

NASA's Radioisotope Power Conversion Technology program is developing next generation power conversion technologies that will enable future missions that have requirements that cannot be met by either the ubiquitous photovoltaic systems or by current Radioisotope Power System (RPS) technology. Performance goals of advanced radioisotope power systems include improvement over the state-of-practice General Purpose Heat Source/Radioisotope Thermoelectric Generator by providing significantly higher efficiency to reduce the number of radioisotope fuel modules, and increase specific power (watts/kilogram). Other Advanced RPS goals include safety, long-life, reliability, scalability, multi-mission capability, resistance to radiation, and minimal interference with the scientific payload. NASA has awarded ten contracts in the technology areas of Brayton, Stirling, Thermoelectric, and Thermophotovoltaic power conversion including five development contracts that deal with more mature technologies and five research contracts. The Advanced RPS Systems Assessment Team includes members from NASA GRC, JPL, DOE and Orbital Sciences whose function is to review the technologies being developed under the ten Radioisotope Power Conversion Technology contracts and assess their relevance to NASA's future missions. Presented is an overview of the ten radioisotope power conversion technology contracts and NASA's Advanced RPS Systems Assessment Team.

Design and simulation of an automation system of a production process and fractionation of 131I, using strategies of advanced control

International Nuclear Information System (INIS)

Paez, Jose; Arias, Pablo; Miranda, Jesus

2013-01-01

In this report, the results are obtained in the design and simulation of a control system using advanced strategies in a production cell in the Plant Production of Radioisotopes of IPEN. The results demonstrate that the temperature of the coalition oven is stabilized after 30 minutes, being constituted in an advantage to obtain the maximum yield of the cell production of 131 I; also, an integral good controller has been designed that allows to obtain a mathematical model that reproduces with enough accuracy the behavior of the process. With the final simulation it has been to demonstrate that the System Control of Temperature of the Cell Production of 131 I is a controllable system and allows to carry out the respective sequence with other variables of control of the production cell. (author)

Radiation Dose-rate Reduction Pattern in Well-differentiated Thyroid Cancer Treated with I-131.

Science.gov (United States)

Khan, Shahbaz Ahmad; Khan, Muhammad Saqib; Arif, Muhammad; Durr-e-Sabih; Rahim, Muhammad Kashif; Ahmad, Israr

2015-07-01

To determine the patterns of dose rate reduction in single and multiple radioiodine (I-131) therapies in cases of well differentiated thyroid cancer patients. Analytical series. Department of Nuclear Medicine and Radiation Physics, Multan Institute of Nuclear Medicine and Radiotherapy (MINAR), Multan, Pakistan, from December 2006 to December 2013. Ninety three patients (167 therapies) with well differentiated thyroid cancer treated with different doses of I-131 as an in-patient were inducted. Fifty four patients were given only single I-131 therapy dose ranging from 70 mCi (2590 MBq) to 150 mCi (5550 MBq). Thirty nine patients were treated with multiple I-131 radioisotope therapy doses ranging from 80 mCi (2960 MBq) to 250 mCi (9250 MBq). T-test was applied on the sample data showed statistically significant difference between the two groups with p-value (p < 0.01) less than 0.05 taken as significant. There were 68 females and 25 males with an age range of 15 to 80 years. Mean age of the patients were 36 years. Among the 93 cases of first time Radio Active Iodine (RAI) therapy, 59 cases (63%) were discharged after 48 hours. Among 39 patients who received RAI therapy second time or more, most were discharged earlier after achieving acceptable discharge dose rate i.e 25 µSv/hour; 2 out of 39 (5%) were discharged after 48 hours. In 58% patients, given single I-131 therapy dose, majority of these were discharged after 48 hours without any major complications. For well differentiated thyroid cancer patients, rapid dose rate reduction is seen in patients receiving second or subsequent radioiodine (RAI) therapy, as compared to first time receiving RAI therapy.

Research and development for the application of radioisotope technology in SINR

International Nuclear Information System (INIS)

Zhang Jiahua

1987-01-01

A brief systematic account on the research and development for the application of radioisotope technology in Shanghai Institute of Nuclear Research (SINR) is presented. It comprehensively covers the following categories: 1. Radioisotopes produced by cyclotron; 2. Radioisotope-labelled compounds; 3. Radioisotope as source of energy converter; 4. Induced-radioisotope generation as a means for elemental analysis--the activation analysis; 5. Radioisotope equipped with electronic instrument for various application; and 6. Special usage of some radioisotopes

Phaeochromocytoma and functioning paraganglioma in childhood and adolescence: Role of iodine 131 metaiodobenzylguanidine

International Nuclear Information System (INIS)

Khafagi, F.A.; Shapiro, B.; Fischer, M.; Sisson, J.C.; Beierwaltes, W.H.; Hutchinson, R.

1991-01-01

Phaeochromocytomas and functioning paragangliomas are rare tumours in childhood and adolescence. We review our experience of 43 cases (24 men, 19 women) who were first diagnosed at the age of ≤ 18 years. All patients were evaluated at some point in their illness, with iodine 131 metaiodobenzylguanidine ( 131 I-mIBG) scintigraphy. Eight patients (19%) had bilateral adrenal tumours, 12 (28%) had solitary extraadrenal tumours, and 8 (19%) had multiple tumours. In 10 patients (23%), the tumours were associated with a familial neurocristopathic syndrome. Thirteen of 24 (54%) unifocal tumours which were initially considered to be benign ultimately proved to be multi-focal and/or malignant. The final prevalence of malignancy was 60% - 26 patients, of whom only 15 (57%) had obviously malignant tumours at the time of diagnosis. Primary tumour size ≥ 5 cm was more commonly associated with a malignant course in adrenal but not extra-adrenal tumours. No other clinical, biochemical or morphological characteristic was significantly associated with malignancy. Although the high prevalence of malignancy in this series at least partly reflects referral bias, the need for lifelong follow-up of these patients is underscored. 131 I-mIBG scintigraphy was positive in 36 patients (84%), with a somewhat lower false-negative rate (12%) than X-ray computed tomography (20%). Eight patients with malignant tumours received therapeutic doses of 131 I-mIBG, with partial tumour responses in 3. Thus, 131 I-mIBG is an efficacious, non-invasive, localising agent and may be considered as a palliative therapeutic agent when alternatives have failed. (orig.)

Radioisotope x-ray fluorescence and neutron activation analyses of the trace element concentrations of the rainbow trout

International Nuclear Information System (INIS)

Akyuz, T.; Bassari, A.; Bolcal, C.; Sener, E.; Yildiz, M.; Kucer, R.; Kaplan, Z.; Dogan, G.; Akyuz, S.

1999-01-01

The muscles and livers of the ten rainbow trouts (Oncorhynchus mykiss; N, 1752) obtained from Sapanca, Aquaculture Facility of Aquatic Products Faculty, The University of Istanbul (Turkey), have been analysed quantitatively for some minor elements using the radioisotope energy dispersive X-ray fluorescence (EDXRF) and neutron activation analysis (NAA) methods. It was found that samples contain Na, K, Ca, Sc, Cs, Fe, Co, Cu, Zn, Se, Br, Rb, Sr, Au, La and Ce in different amounts. Comparison of the results with those of reference river fish samples indicated that agricultural rainbow trout samples from Sapanca region have higher Fe level. (author)

Radioisotope X-ray fluorescence and neutron activation analyses of the trace element concentrations of the rainbow trout

Science.gov (United States)

Akyuz, T.; Bassari, A.; Bolcal, C.; Sener, E.; Yildiz, M.; Kucer, R.; Kaplan, Z.; Dogan, G.; Akyuz, S.

1999-01-01

The muscles and livers of the ten rainbow trouts ( Oncorhynchus mykiss; N, 1752) obtained from Sapanca, Aquaculture Facility of Aquatic Products Faculty, The University of Istanbul (Turkey), have been analysed quantitatively for some minor elements using the radioisotope energy dispersive X-ray fluorescence (EDXRF) and neutron activation analysis (NAA) methods. It was found that samples contain Na, K, Ca, Sc, Cs, Fe, Co, Cu, Zn, Se, Br, Rb, Sr, Au, La and Ce in different amounts. Comparison of the results with those of reference river fish samples indicated that agricultural rainbow trout samples from Sapanca region have higher Fe level.

External dose measurements for patients receiving therapeutic I-131 for thyroid cancer

International Nuclear Information System (INIS)

Molfetas, M.; Kottou, S.

2002-01-01

Iodine-131 is a well established and effective treatment, supplementing surgery, in differentiated thyroid carcinoma. Iodine-131 except from its β-emission, that generates a cell-killing effect in a small area, has also a γ-emission irradiating distant tissues and even people who are close enough with the treated patient. The International Commission on Radiation Protection, ICRP has estimated the probability of a radiation-induced fatal cancer for the whole population at 5.0 % per sievert for low doses and at low dose rates and at 1.3 % for serious genetic diseases. For elderly people the probability seems to be 3 to 10 times lower, whereas for children up to the age of 10 years, 2-3 times higher. These findings led the ICRP to recommend new dose limits, lower than the previous ones. The European Union has endorsed the ICRP recommendations and the Council issued two directives, with which the Greek legislation complied recently. The current annual public dose limit is 1 mSv, while in the new Greek legislation the concept of dose constrains (0.5 m Sv in Greece) has also been proposed as a goal to reach whenever possible

Radioisotope clocks in archaeology

Energy Technology Data Exchange (ETDEWEB)

Hedges, R E.M. [Oxford Univ. (UK). Research Lab. for Archaeology

1979-09-06

Methods of absolute dating which use the rate of disintegration of a radioactive nucleus as the clock, are reviewed. The use of the abundant radioisotopes (/sup 40/K, Th and U) and of the rare radioisotopes (/sup 14/C, /sup 10/Be, /sup 26/Al, /sup 32/Si, /sup 36/Cl, /sup 41/Ca, /sup 53/Mn) is discussed and radiation integration techniques (fission track dating, thermoluminescence and related techniques) are considered. Specific fields of use of the various methods and their accuracy are examined.

Packaging and transport of radioisotopes

International Nuclear Information System (INIS)

Taylor, C.B.G.

1976-01-01

The importance of radioisotope traffic is emphasized. More than a million packages are being transported each year, mostly for medical uses. The involvement of public transport services and the incidental dose to the public (which is very small) are appreciably greater than for movements connected with the nuclear fuel cycle. Modern isotope packages are described, and an outline given of the problems of a large radioisotope manufacturer who has to package many different types of product. Difficulties caused by recent uncoordinated restrictions on the use of passenger aircraft are mentioned. Some specific problems relating to radioisotope packaging are discussed. These include the crush resistance of Type A packages, the closure of steel drums, the design of secure closures for large containers, the Type A packaging of liquids, leak tightness criteria of Type B packages, and the use of 'unit load' overpacks to consign a group of individually approved packages together as a single shipment. Reference is made to recent studies of the impact of radioisotope shipments on the environment. Cost/benefit analysis is important in this field - an important public debate is only just beginning. (author)

Uses of radioisotopes in Sudan

International Nuclear Information System (INIS)

Elradi, E. A. M.

2013-07-01

In this research project, an inventory for the different radioisotopes that were imported by public and private sectors of Sudan in the period between ( 2007-2011) has been set up. These organizations import the appropriates for different but in general we classify them into these applications: Medical, Industrial, Agricultural and Research. However, each broad discipline is subdivided into subgroups. This inventory will help those who are willing to establish research reactors in Sudan on the type and power of the reactors to be purchases according to the actual needs of Sudan with forecasting of the near and for future needs. Also the expenditure that has been spent by these organizations have been estimated for most of the radioisotopes. It was observed that almost 50% of the expenditure went for the fright charges as these radioisotopes need special handling and care by installing a research reactor in Sudan, the cost of purchasing will be cut down several folds. Also it will help in availability of the radioisotopes with very short half lives (hours to days). This will be reflected in the cut down the cost of tests and provision of new tests.(Author)

Seasonal variation of the Cs137 contamination of the tree forage of wild hoofed animals of the Pripyat National Park

International Nuclear Information System (INIS)

Uglyanets, A.V.

2011-01-01

In the conditions of the Republic of Belarus there were presented the results of studies of the 137Cs contamination of the tree forage of wild hoofed animals in the Pripyat national park. The parameters of this radioisotope accumulation in the shoots of different trees, shrubs, dwarf shrubs and bushes were studied in the seasonal and edaphic aspects, and their influencing factors were specified. The 137Cs contamination of the tree forage of wild hoofed animals was determined to be dependent on the soil pollution degree, growth conditions and species composition of plants and their proportion in the phytocenosis, as well as on the edaphic conditions and a season of the year

Radioisotope studies utilizing a low level whole body counter and clinical applications of activation analysis. Progress report. [Nuclear medicine research studies

Energy Technology Data Exchange (ETDEWEB)

Brill, A.B.

1976-04-30

Design modifications in radioisotope scanners are discussed. Studies on the radiation dose distribution in patients from /sup 90m/Tc-albumin microspheres in the lungs, /sup 59/Fe-citrate, /sup 131/I-hippuran in kidney transplants, and /sup 99m/Tc-pyrophosphates are reported. Data on the levels of fallout /sup 137/Co in normal individuals during 1975, as measured by whole-body counting, are reported. Results of studies on iodine metabolism in patients with hyperthyroidism and with T/sub 3/-thyrotoxicosis during /sup 131/I therapy with activities up to 17 mCi showed that the apparent volumes of distribution for different iodine compounds do not change appreciably during therapy in this dose range. Methods are described for measuring the content of Ca alone and Ca and P in bone tissues by transmission scanning using a /sup 252/Cf neutron source for activation of Ca and P. (CH)

Evaluation of the population dose due to the gaseous emission of a radioisotopes production unit

International Nuclear Information System (INIS)

Gordon, A.M.P.L.; Jacomino, V.M.F.; Sordi, G.-M.A.A.

1990-05-01

In order to control the emission of gaseous radioactive iodine from the unit responsible for the production of radioisotopes of IPEN-CNEN/SP, a discharge monitoring is carried out. In 1988 an activity of 65 GBq of I-131 was discharged to the environment. Based upon this value and the site analysis, the effective equivalent dose in the general public was evaluated for normal operation and for an incidental discharge. The evaluation was carried out by using a diffusion atmospheric model, 500 to 7000 m away from the discharge point and using 8 different wind direction sectors. The critical group was identified as being the people who lives 3000 m far from the discharge point, in the diffusion sector NW. The dose evaluated at this point is 10 9 times lower than the annual dose limit for individual of the public, according to Radiological Protection Standards. The derived limit for discharge of iodine was also evaluated and it was concluded that the IPEN-CNEN/SP can increase their production up to a level which results in an annual discharge of 1,5 x 10 12 of I-131. (author) [pt

4. Quarterly progress report, 1978

International Nuclear Information System (INIS)

1978-01-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

4. Quarterly progress report, 1977

International Nuclear Information System (INIS)

1977-01-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

4. Quarterly progress report 1981

International Nuclear Information System (INIS)

1981-01-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. the activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

3. Quaterly progress report, 1980

International Nuclear Information System (INIS)

1980-01-01

This quaterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

NATO Allied Medical Publication 7.5 (AMedP 7.5) NATO Planning Guide for the Estimation of CBRN Casualties

Science.gov (United States)

2016-12-01

PROMULGATION [ Date ] 1. The enclosed Allied Medical Publication AMedP-7.5, NATO Planning Guide for the Estimation of CBRN Casualties, which has been... radioisotopes modeled are 60Co, 90Sr, 99Mo, 125I, 131I, 137Cs, 192Ir, 226Ra, 238Pu, 241Am, 252Cf. 2) Whole-body irradiation (from cloudshine, groundshine,9... Earth Shelter 16.67 66.67 Exposed/Dismounted 1.00 1.00 Foxhole (nuclear only)† 3.00 10.00 Masonry Building 8.33 6.67 Multi-Story Brick Building 1.33

3. Quarterly progress report, 1981

International Nuclear Information System (INIS)

1981-01-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

2. Quaterly progress report, 1980

International Nuclear Information System (INIS)

1980-01-01

This quaterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

3. Quarterly progress report, 1977

International Nuclear Information System (INIS)

1977-01-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, undergroung water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

1. Quaterly progress report, 1981

International Nuclear Information System (INIS)

1981-01-01

This quaterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

4. Quaterly progress report, 1980

International Nuclear Information System (INIS)

1980-01-01

This quaterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmosheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

3. Quarterly progress report, 1983

International Nuclear Information System (INIS)

1983-07-01

This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables ( 7 Be, 95 Zr and 95 Nb, 103 Ru, 131 I, 137 Cs, 140 Ba and 140 La, 90 Sr, 106 Ru and 106 Rh, 226 Ra, 54 Mn, U and T). A bibliographic selection is also presented [fr

Sediment radioisotope dating across a stratigraphic discontinuity in a mining-impacted lake.

Science.gov (United States)

McDonald, C P; Urban, N R

2007-01-01

Application of radioisotope sediment dating models to lakes subjected to large anthropogenic sediment inputs can be problematic. As a result of copper mining activities, Torch Lake received large volumes of sediment, the characteristics of which were dramatically different from those of the native sediment. Commonly used dating models (CIC-CSR, CRS) were applied to Torch Lake, but assumptions of these methods are violated, rendering sediment geochronologies inaccurate. A modification was made to the CRS model, utilizing a distinct horizon separating mining from post-mining sediment to differentiate between two focusing regimes. (210)Pb inventories in post-mining sediment were adjusted to correspond to those in mining-era sediment, and a sediment geochronology was established and verified using independent markers in (137)Cs accumulation profiles and core X-rays.

Novel Radioisotope Applications in Industry Promoted by the IAEA

International Nuclear Information System (INIS)

Thereska, J.

2001-01-01

Presently, there is a lively activity in further development and use of radioisotope technology. Novel radioisotope applications in industry are promoted by the IAEA. Radioisotope technology is contributing significantly to improving and optimising process performance bringing an annual economic benefit to world-wide industry of several billion US$. Probably, an average benefit to cost ratio of 40:1 is reasonably representative of radioisotope applications in industry. There are few short-term investments, which will give a return of this magnitude. The cost effectiveness of radioisotope applications should be widely promulgated to encourage industrialists to take full advantage of the technology. (author)

CS Informativeness Governs CS-US Associability

Science.gov (United States)

Ward, Ryan D.; Gallistel, C. R.; Jensen, Greg; Richards, Vanessa L.; Fairhurst, Stephen; Balsam, Peter D

2012-01-01

In a conditioning protocol, the onset of the conditioned stimulus (CS) provides information about when to expect reinforcement (the US). There are two sources of information from the CS in a delay conditioning paradigm in which the CS-US interval is fixed. The first depends on the informativeness, the degree to which CS onset reduces the average expected time to onset of the next US. The second depends only on how precisely a subject can represent a fixed-duration interval (the temporal Weber fraction). In three experiments with mice, we tested the differential impact of these two sources of information on rate of acquisition of conditioned responding (CS-US associability). In Experiment 1, we show that associability (the inverse of trials to acquisition) increases in proportion to informativeness. In Experiment 2, we show that fixing the duration of the US-US interval or the CS-US interval or both has no effect on associability. In Experiment 3, we equated the increase in information produced by varying the C̅/T̅ ratio with the increase produced by fixing the duration of the CS-US interval. Associability increased with increased informativeness, but, as in Experiment 2, fixing the CS-US duration had no effect on associability. These results are consistent with the view that CS-US associability depends on the increased rate of reward signaled by CS onset. The results also provide further evidence that conditioned responding is temporally controlled when it emerges. PMID:22468633

Evaluation of results of more than 20 years treating hyperthyroidism by I-131

International Nuclear Information System (INIS)

Phan, S.A.; Mai, T.K.; Tran, D.H.

2001-01-01

The authors have summarized their works of more than 20 years using I-131 for treatment and close observation of 723 patients with hyperthyroidism in 1000 ones in the Nuclear Medicine Department, Bach Mai University Hospital in Hanoi to collect data and draw experience for the report. Patient selection for the treatment is based on clinical features and laboratory tests results by the Nuclear Medicine Department such as thyroid uptake, scintigraphy and RIA determinations of thyroid hormones. I-131 dose is determined in compliance with a prevailing formula. The average dose is 6.2 ± 1.1 mCi (that is 233.1 ± 40.7 MBq). The average number of times is 1.3 time for one patient. The results are as follows: Euthyroid status after 4- year following- up from date of I-131 dose administration: 72.3%; Persistent or recurrent hyperthyroidism: 20.0%; Hypothyroid complications: appear 4 to 12 months after date of I-131 administration: 3.0%; appear 4 years after date of I-131 administration: 7.7%; appear 6 years after date of I-131 administration. 14.0%; so the cumulative hypothyroid rate is 2.3% per year. No occurrence of other serious complications by all the observed patients. This is therefore a safe, efficient treatment method to be applied on a large scale including adolescents and children. However, much more study has still to be made on the dose due to high rate of recurrence of the therapeutic method although the hypothyroid complications cases are not serious. Hyperthyroidism is a common health problem in Viet Nam. Previously, only anti-thyroid drugs and surgery were used. Use of I-131 was firstly introduced to Viet Nam in the Nuclear Medicine Department in Bach Mai in 1974 and afterwards applied larger nationwide. Initial therapeutic results have been published in national medical magazines. This is a general study aiming at analyzing the way to carry out the work and get experience and recommendation from gained results for further work in the future. (author)

Radioisotopes in soil science

International Nuclear Information System (INIS)

Kotur, S.C.

2004-01-01

Soils form a thin veneer of the Earth that sustain the entire flora and fauna of the terra firma. To that extent the soil as a natural resource is very precious and needs to be managed in a sustainable manner. The fate of degradation of pesticides in soil and build-up of heavy metals in the overall biosafety scenario is also studied gainfully using radioisotopes. Radioisotopes are a very potent tool in the hands of the Soil Scientists, perhaps, the most important among the peaceful applications in service of the mankind

Separation of Radioiodine Fraction in the Processing Line of 235U Fission Produced 99Mo and Its Utilization For Preparation of Hippuran131I

International Nuclear Information System (INIS)

Soenarjo Sunarhadijoso; HG Adang; W Kadarismanto; Purwadi B; Sukmana A; Sriyono; Rukman

1998-01-01

Production process of 99Mo from fission of 235U in RPC- BATAN produces non-moly radioactive fractions, which are classifiable into 3 fraction, i.e.; radioiodine fraction, radioxenon (noble gas) fraction and post-irradiated uranium fraction. The radioiodine fraction is expectable to be used as a source for providing radioisotope of 131I, and, therefore, an effort for separation of the radioiodine fraction was carried out. The separation was performed by trapping the radioiodine in a copper-wool column followed by purification using charcoal column. The bulk solution of Na131I bulk solution was relatively low, presumable due to the escape of the radioiodine from the copper-wool column into the cold finger originally used for trapping the noble gas fraction

Radioisotopes and their applications in highway testings

International Nuclear Information System (INIS)

Saxena, S.C.

1974-01-01

Applications of radioisotopes in highway testing are described. Radioisotopic methods have been used to determine : (1) moisture and density of soil and base materials for compaction control, (2) magnesium oxide content of cement, (3) permeability of bituminous coverings and (4) field density of freshly laid hot bituminous concrete surface. Possible uses of nuclear explosives for production of aggregates and of radioisotopes for determination of deflection in the design of flexible pavements are indicated. (M.G.B.)

The {sup 131}I cytogenetic effect preceded by the REC-HTSH administration in Wistar rats; Efeito citogenetico do {sup 131}I precedido por administracao de Rec-hTSH em ratos Wistar

Energy Technology Data Exchange (ETDEWEB)

Silva, Marcia Augusta da [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]|[Centro Universitario Sao Camilo, Sao Paulo, SP (Brazil); Ribela, Maria Teresa Carvalho Pinto; Suzuki, Miriam Fussae; Bartolini, Paolo; Okazaki, Kayo [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: kokazaki@ipen.br; Guimaraes, Maria Ines Calil Cury; Buchpiguel, Carlos Alberto [Sao Paulo Univ., SP (Brazil). Centro de Medicina Nuclear]. E-mail: maria.ins@hcnet.usp.br

2005-07-01

In nuclear medicine, the {sup 131}I is one of the most used radionuclides in thyroid disorders, for both diagnostic and therapeutic purposes. The target of the present study was to analyze the cytogenetic effects of the {sup 131}I, precede by stimulus with rec-hTSH, produced at IPEN/CNEN-SP, in an animal model by means of the chromosome aberration technique. The rec-hTSH is a glycoprotein administered in patients submitted to thyroidectomy as an alternative to the suspension of the hormone therapy for increasing the TSH level and, consequently, the {sup 131}I collection by the metastatic tissue, thus maintaining the euthyroid state. For this aim, Wistar rats were used (SPF, females, 200 g heavy), divided in 2 groups: animals treated only with {sup 131}I (G1) (11.1 MBq gastric gavage) and animals submitted to rec-hTSH-IPEN (1.2 {mu}g by intramuscular injection), 24 hours before the {sup 131}I (G2) administration. The blood samples were collected before (basal), 24 hours, 1 week and 1 month after the treatment, for cytogenetic evaluation. The cytogenetic data obtained showed an increase un the frequency of cells with chromosome aberration as well as the number of chromosome/cell aberrations, 24 hours after the {sup 131}I administration, when compared with the basal values, both for animals in group G1 and for in group G2. After 7 and 30 days of the radioiodine administration, a slight fall in the frequency of the chromosome aberrations was verified. The animals pre-treated with rec-hTSH-IPEN showed higher percentage of cells with chromosome aberration and chromosome/cell aberrations than the animals of group G1, in both de 24 hour-after administration of {sup 131}I samples and 7 day-sample, although the difference is not statistically significant (p>0,05). The results obtained allow the extrapolation for humans, in the more accurate evaluation of the biological risks involved by people exposed to the radioiodine, and also for the optimizations of a therapeutic

Medical Radioisotope Scanning, Vol. II. Proceedings of the Symposium on Medical Radioisotope Scanning

International Nuclear Information System (INIS)

1964-01-01

Medical applications of radioisotopes continue to grow in number and importance and medical centres in almost all countries of the world are now using radioactive materials both in the diagnosis and treatment of disease. An increasing proportion of these applications involves studies of the spatial distribution of radioactive material within the human body, for which purpose highly specialized scanning methods have been elaborated. By these methods it is possible to study the position, size and functional state of different organs, to detect tumours, cysts and other abnormalities and to obtain much useful information about regions of the body that are otherwise inaccessible, except by surgery. Progress in scanning methods in recent years has been very rapid and there have been many important advances in instrumentation and technique. The development of new forms of the gamma camera and of colour-scanning techniques are but two examples of recent improvements. The production of new radioisotopes and new labelled compounds has further extended the scope of these methods. To survey these new advances the International Atomic Energy Agency held a Symposium on Medical Radioisotope Scanning in Athens from 20-24 April 1964. The scientific programme of the meeting covered all aspects of scanning methods including theoretical principles, instrumentation, techniques and clinical applications. The World Health Organization assisted in the selection of papers by providing a consultant to the selection committee. The meeting followed the earlier IAEA/WHO Seminar on Medical Radioisotope Scanning in Vienna in 1959, which was attended by 36 participants and at which 14 papers were presented. Some idea of the growth of interest in the subject may be gained from the fact that the Symposium was attended by 160 participants from 26 countries and 4 international organizations, and that 58 papers were presented. The published proceedings, comprising two volumes, contain all the

Validation of the TRMM Multi Satellite Rainfall Product 3B42 and estimation of scavenging coefficients for (131)I and (137)Cs using TRMM 3B42 rainfall data.

Science.gov (United States)

Shrivastava, R; Dash, S K; Hegde, M N; Pradeepkumar, K S; Sharma, D N

2014-12-01

The TRMM rainfall product 3B42 is compared with rain gauge observations for Kaiga, India on monthly and seasonal time scales. This comparison is carried out for the years 2004-2007 spanning four monsoon seasons. A good correlation is obtained between the two data sets however; magnitude wise, the cumulative precipitation of the satellite product on monthly and seasonal time scales is deficient by almost 33-40% as compared to the rain gauge data. The satellite product is also compared with APHRODITE's Monsoon Asia data set on the same time scales. This comparison indicates a much better agreement since both these data sets represent an average precipitation over the same area. The scavenging coefficients for (131)I and (137)Cs are estimated using TRMM 3B42, rain gauge and APHRODITE data. The values obtained using TRMM 3B42 rainfall data compare very well with those obtained using rain gauge and APHRODITE data. Copyright © 2014 Elsevier Ltd. All rights reserved.

137Cs source dose distribution using the Fricke Xylenol Gel dosimetry

International Nuclear Information System (INIS)

Sato, R.; De Almeida, A.; Moreira, M.V.

2009-01-01

Dosimetric measurements close to radioisotope sources, such as those used in brachytherapy, require high spatial resolution to avoid incorrect results in the steep dose gradient region. In this work the Fricke Xylenol Gel dosimeter was used to obtain the spatial dose distribution. The readings from a 137 Cs source were performed using two methods, visible spectrophotometer and CCD camera images. Good agreement with the Sievert summation method was found for the transversal axis dose profile within uncertainties of 4% and 5%, for the spectrophotometer and CCD camera respectively. Our results show that the dosimeter is adequate for brachytherapy dosimetry and, owing to its relatively fast and easy preparation and reading, it is recommended for quality control in brachytherapy applications.

Sequelae and survivorship in patients treated with (131)I-MIBG therapy.

Science.gov (United States)

Sze, W C C; Grossman, A B; Goddard, I; Amendra, D; Shieh, S C C; Plowman, P N; Drake, W M; Akker, S A; Druce, M R

2013-08-06

(131)I-meta-iodobenzylguanidine ((131)I-MIBG) has been in therapeutic use since 1980s. Newer treatment modalities are emerging for neuroendocrine tumours (NETs) and chromaffin cell tumours (CCTs), but many of these do not yet have adequate long-term follow-up to determine their longer term efficacy and sequelae. Fifty-eight patients with metastatic NETs and CCTs who had received (131)I-MIBG therapy between 2000 and 2011 were analysed. Survival and any long-term haematological or renal sequelae were investigated. In the NET group, the overall median survival and median survival following the diagnosis of metastatic disease was 124 months. The median survival following the commencement of (131)I-MIBG was 66 months. For the CCT group, median survival had not been reached. The 5-year survival from diagnosis and following the diagnosis of metastatic disease was 67% and 67.5% for NETs and CCTs, respectively. The 5-year survival following the commencement of (131)I-MIBG therapy was 68%. Thirty-two patients had long-term haematological sequelae: 5 of these 32 patients developed haematological malignancies. Two patients developed a mild deterioration in renal function. Long follow up of (131)I-MIBG therapy reveals a noteable rate of bone marrow toxicities and malignancy and long term review of all patients receiving radionuclide therapies is recommended.

Economical Radioisotope Power

Data.gov (United States)

National Aeronautics and Space Administration — Almost all robotic space exploration missions and all Apollo missions to the moon used Radioisotopic Thermoelectric Generators (RTGs) to provide electrical power to...

Natural gamma radioactivity and of {sup 137} Cs in soil of the Chimaltitan municipality, Jalisco, Mexico; Radiactividad gamma natural y del {sup 137} Cs en suelo del Municipio de Chimaltitan, Jalisco, Mexico

Energy Technology Data Exchange (ETDEWEB)

Garay, A.; Mireles, F.; Quirino, L.L.; Davila, J.I.; Rios, C.; Lugo, J.F.; Soriano, J.M.; Angoli, A. [UAEN-Universidad Autonoma de Zacatecas, Cipres 10, Frac. La Penuela, 98000 Zacatecas (Mexico)]. e-mail: albinogaray@hotmail.com.mx

2003-07-01

With the purpose of determining the activity due to the natural presence of the {sup 226} Ra, {sup 232} Th, {sup 40} K and {sup 137} Cs in soil samples, of the municipality of Chimaltitan Jalisco. A set of these samples was measured in a gamma ray spectrometric system based on a High-purity Germanium detector. It is well-known that approximately 87% of the dose of the received radiation by the population is due to sources of natural radiation and 13% of the anthropogenic radiation. The gamma radiation comes mainly from the {sup 40} K and of those radionuclides of the series of radioactive decay of {sup 238} U and {sup 232} Th that its find dispersed thoroughly in the terrestrial crust. In this work its were analyzed twenty-two soil samples. It is enlarged the activity characterization for the radioisotopes of {sup 226} Ra {sup 232} Th, {sup 40} K and {sup 137} Cs. (Author)

One-year, regional-scale simulation of 137Cs radioactivity in the ocean following the Fukushima Dai-ichi Nuclear Power Plant accident

Directory of Open Access Journals (Sweden)

D. Tsumune

2013-08-01

Full Text Available A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant following the Great East Japan Earthquake and tsunami of 11 March 2011 resulted in the release of radioactive materials to the ocean by two major pathways: direct release from the accident site and atmospheric deposition. A 1 yr, regional-scale simulation of 137Cs activity in the ocean offshore of Fukushima was carried out, the sources of radioactivity being direct release, atmospheric deposition, and the inflow of 137Cs deposited into the ocean by atmospheric deposition outside the domain of the model. Direct releases of 137Cs were estimated for 1 yr after the accident by comparing simulated results and measured activities adjacent to the accident site. The contributions of each source were estimated by analysis of 131I/137Cs and 134Cs/137Cs activity ratios and comparisons between simulated results and measured activities of 137Cs. The estimated total amounts of directly released 131I, 137Cs, and 137Cs were 11.1 ± 2.2 PBq, 3.5 ± 0.7 PBq, and 3.6 ± 0.7 PBq, respectively. Simulated 137Cs activities attributable to direct release were in good agreement with measured 137Cs activities not only adjacent to the accident site, but also in a wide area in the model domain, therefore this implies that the estimated direct release rate was reasonable. Employment of improved nudging data by JCOPE2 improved both the offshore transport result and the reproducibility of 137Cs activities 30 km offshore. On the other hand, simulated 137Cs activities attributable to atmospheric deposition were low compared to measured activities. The rate of atmospheric deposition into the ocean was underestimated because of a lack of measurements of deposition into the ocean when atmospheric deposition rates were being estimated. Simulated 137Cs activities attributable to the inflow of 137Cs deposited into the ocean outside the domain of the model were in good agreement with measured activities in the open

Radioisotope thermoelectric generators for implanted pacemakers

Energy Technology Data Exchange (ETDEWEB)

Pustovalov, A.A.; Bovin, A.V.; Fedorets, V.I.; Shapovalov, V.P.

1986-08-01

This paper discusses the development and application of long-life lithium batteries and the problems associated with miniature radioisotope thermoelectric generators (RITEG) with service lives of 10 years or longer. On eof the main problems encountered when devising a radioisotope heat source (RHS) for an RITEG is to obtain biomedical /sup 238/PuO/sub 2/ with a specific neutron yield of 3.10/sup 3/-4.10/sup 3/ (g /SUP ./ sec)/sup -1/, equivalent to metallic Pu 238, and with a content of gamma impurities sufficient to ensure a permissible exposure a permissible exposure does rate (EDR) of a mixture of neutron and gamma radiation. After carrying out the isotope exchange and purifying the initial sample of its gamma impurity elements, the authors obtain biomedical Pu 238 satisfying the indicated requirements king suitable for use in the power packs of medical devices. Taking the indicated specifications into account, the Ritm-1o and gamma radioisotope heat sources were designed, built, tested in models and under natural conditions, and then into production as radioisotope thermoelectric generators designed to power the electronic circuits of implanted pacemakers. The Ritm-MT and Gemma radioisotope thermoelectric generators described are basic units, which can be used as self-contained power supplies for electronic equipment with power requirements in the micromilliwatt range.

Biological (DB) and internal dosimetry (DI) in patients with differentiated thyroid carcinoma (CaDT) treated with iodine 131

International Nuclear Information System (INIS)

Fadel, Ana M.; Chebel, G.; Oneto, A.; Di Giorgio, Marina; Vallerga, Maria B.; Taja, Maria R.; Radl, A.; Rojo, Ana M.; Deluca, G.; Levi de Cabrejas, Mariana; Cabrejas, Raul C.

2009-01-01

The internal 131 I radiotherapy in patients with CaDT is used within the therapeutic scheme as a step post-thyroidectomy. The success of therapy is to achieve a lethal dose in the tumor tissue without exceeding the dose of tolerance in healthy tissues (doses greater than 2 Gy in bone marrow could lead to myelotoxicity). In this work, the treatment protocol applied incorporates assessment by biological (DB) and internal dosimetry (DI) for estimating doses to the whole body and bone marrow to administer a therapeutic personalized for each patient. The estimate biological dose is based in the quantification of chromosomal aberrations, which is referred to a dose-response curve. Objectives: 1) To estimate the absorbed dose to the whole body and bone marrow due to the administration of 131 I therapy in patients with CaDT, by applying three different cytogenetic tests: conventional cytogenetics, micronuclei (MN) and fluorescence in situ hybridization (FISH); 2) Assess the correlation of the results obtained by DB and DI for personalization of treatment. Materials and methods: We evaluated 24 patients with CaDiT by applying the cytogenetic tests mentioned and internal dosimetry (methodology Mird-Olinda). Internal dosimetry: We administered a tracer dose 74 to 111 MBq. Measurements were made of activity in whole body and blood. By adjusting the scheme was estimated MIRD dose in bone marrow and the maximum therapeutic activity to manage and secure. Through software Olinda was determined absorbed dose to the whole body for each patient. We considered patient-specific data (physical frame size, weight, hematocrit) to adjust the methodology in each particular case. It is assumed that the tracer activity administered has a kinetic in the body similar to the 131 I to be administered in therapeutic amounts. Biology Dosimetry : We performed for each patient taking 2 sequential venous blood samples to estimate the dose due to therapeutic activity in review: the first shows, pre

Molecular structures and thermodynamic properties of 12 gaseous cesium-containing species of nuclear safety interest: Cs 2, CsH, CsO, Cs 2O, CsX, and Cs 2X 2 (X = OH, Cl, Br, and I)

Science.gov (United States)

Badawi, Michael; Xerri, Bertrand; Canneaux, Sébastien; Cantrel, Laurent; Louis, Florent

2012-01-01

Ab initio electronic structure calculations at the coupled cluster level with a correction for the triples extrapolated to the complete basis set limit have been made for the estimation of the thermochemical properties of Cs 2, CsH, CsO, Cs 2O, CsX, and Cs 2X 2 (X = OH, Cl, Br, and I). The standard enthalpies of formation and standard molar entropies at 298 K, and the temperature dependence of the heat capacities at constant pressure were evaluated. The calculated thermochemical properties are in good agreement with their literature counterparts. For Cs 2, CsH, CsOH, Cs 2(OH) 2, CsCl, Cs 2Cl 2, CsBr, CsI, and Cs 2I 2, the calculated ΔfH298K∘ values are within chemical accuracy of the most recent experimental values. Based on the excellent agreement observed between our calculated ΔfH298K∘ values and their literature counterparts, the standard enthalpies of formation at 298 K are estimated to be the following: ΔfH298K∘ (CsO) = 17.0 kJ mol -1 and ΔfH298K∘ (Cs 2Br 2) = -575.4 kJ mol -1.

Radioisotope production linac

International Nuclear Information System (INIS)

Stovall, J.E.; Hansborough, L.D.; O'Brien, H.A.

1981-01-01

A 70-MeV proton beam would open a new family of medical radioisotopes (including the important 123 I) to wide application. A 70-MeV, 500-μA linac is described, based on recent innovations in accelerator technology. It would be 27.3 m long, cost approx. $6 million, and the cost of power deposited in the radioisotope-production target is comparable to existing cyclotrons. By operating the rf-power system to its full capability, the same accelerator is capable of producing a 1140-μA beam, and the cost per beam watt on the target is less than half that of comparable cyclotrons. The technology to build such a linac is in a mature stage of developmnt, ready for use by industry

Natural gamma radioactivity and of 137 Cs in soil of the Chimaltitan municipality, Jalisco, Mexico

International Nuclear Information System (INIS)

Garay, A.; Mireles, F.; Quirino, L.L.; Davila, J.I.; Rios, C.; Lugo, J.F.; Soriano, J.M.; Angoli, A.

2003-01-01

With the purpose of determining the activity due to the natural presence of the 226 Ra, 232 Th, 40 K and 137 Cs in soil samples, of the municipality of Chimaltitan Jalisco. A set of these samples was measured in a gamma ray spectrometric system based on a High-purity Germanium detector. It is well-known that approximately 87% of the dose of the received radiation by the population is due to sources of natural radiation and 13% of the anthropogenic radiation. The gamma radiation comes mainly from the 40 K and of those radionuclides of the series of radioactive decay of 238 U and 232 Th that its find dispersed thoroughly in the terrestrial crust. In this work its were analyzed twenty-two soil samples. It is enlarged the activity characterization for the radioisotopes of 226 Ra 232 Th, 40 K and 137 Cs. (Author)

Intra-arterial injection of iodine-131-labeled lipiodol for treatment of hepatocellular carcinoma

International Nuclear Information System (INIS)

Boucher, Eveline; Garin, Etienne; Guylligomarc'h, Anne; Olivie, Damien; Boudjema, Karim; Raoul, Jean-Luc

2007-01-01

Background/Aim: The therapeutic effect of intra-arterial injection of 131-iodine-labeled lipiodol for treatment of hepatocellular carcinoma in palliative or adjuvant settings has been promising. We report, the results of an open study of this therapy in cirrhotic patients with small hepatocellular carcinoma. Patients and method: Forty patients with hepatocellular carcinoma were given intra-arterial injections of 131-iodine-labeled lipiodol. These injections were repeated if necessary every 3 months. Tumor response (WHO criteria) was determined on CT scans performed after each treatment and every 3 months during the follow-up. Side effects and the cause of death were recorded. Therapeutic response and survival were analyzed. Results: The median number of treatment was 2 (1-4). There was one complete response, 18 partial responses (47.5% response rate); 19 had stable disease and 2 progressions. Overall survival rates (±CI 95%) at 1, 2 and 3 years were: 90 ± 4.7%, 60.3 ± 8%, and 39 ± 8.3%, respectively. Median survival was 27 months; 25 patients have died (4-56 months), 8 of tumor progression with a multifocal spread in the liver. Tolerance was good except for 2 patients who develop a fatal drug-related pulmonary insufficiency. Conclusion: These data suggest that intra-arterial therapeutic injection of 131-iodine-labeled lipiodol for treatment of hepatocellular carcinoma can provide high rate response and long survival for individuals not eligible for surgery or local treatment

Investigation of Radioiodination of Meta-Iodobenzylguanidine Compound with 131I Isotope in Solid Phase Using Cu Catalyzer

International Nuclear Information System (INIS)

Davarpanah, M. R.; Attar Nosrati, S.; Khoshhosn, H.; Kazemi Boudani, M.; Fazlali, M.; Ghannadi Maragheh, M.

2012-01-01

In this study the radioiodination process of meta-iodobenzylguanidine with 131 I isotope in presence of ammonium sulphate and Cu(II) Catalyzer was investigated. In order to optimize the process, the influence of different parameters on labeling yield was studied. The results of experiments showed that the use of oil bath with temperature of 160 d egree C is necessary. After the labeling process, purification step of the final product was carried out using Dowex-1 x 8 resin. The mean labeling yield was 97.2 p ercent . In this method radiolabelling of MIBG with 131 I (185 MBq for diagnostic dose and 3330 MBq for therapeutic dose) is quite simple and it complies with the requirements of routine production of 13 1I-MIBG radiopharmaceutical for diagnostic and therapeutic purposes. This paper is a narration of industrial scale production of 131 I-MIBG radiopharmaceutical.

Industrial applications of radioisotope tracers

International Nuclear Information System (INIS)

Easey, J.F.

1985-01-01

Radioisotope tracing techniques are powerful tools for analysing the behaviour of large systems and investigating industrially or economically important processes. The results of radioisotope experiments can yield important information, for example, on parameters such as flow rates, mixing phenomena, flow abnormalities and leaks. Some examples of current AAEC research are described, covering studies on hearth drainage in blast furnaces, flow behaviour in waste-water treatment ponds, and sediment transport in marine environments

Assessment of radioisotope heaters for remote terrestrial applications

International Nuclear Information System (INIS)

Uherka, K.L.

1987-05-01

This paper examines the feasibility of using radioisotope byproducts for special heating applications at remote sites in Alaska and other cold regions. The investigation included assessment of candidate radioisotope materials for heater applications, identification of the most promising cold region applications, evaluation of key technical issues and implementation constraints, and development of conceptual heater designs for candidate applications. Strontium-90 (Sr-90) was selected as the most viable fuel for radioisotopic heaters used in terrestrial applications. Opportunities for the application of radioisotopic heaters were determined through site visits to representative Alaska installations. Candidate heater applications included water storage tanks, sludge digesters, sewage lagoons, water piping systems, well-head pumping stations, emergency shelters, and fuel storage tank deicers. Radioisotopic heaters for water storage tank freeze-up protection and for enhancement of biological waste treatment processes at remote sites were selected as the most promising applications

Dosimetry-guided high-activity 131I therapy in patients with advanced differentiated thyroid carcinoma: initial experience

International Nuclear Information System (INIS)

Verburg, Frederik A.; Haenscheid, Heribert; Biko, Johannes; Hategan, Maria C.; Lassmann, Michael; Kreissl, Michael C.; Reiners, Christoph; Luster, Markus

2010-01-01

In patients with advanced differentiated thyroid carcinoma (DTC), therapy with the highest safe 131 I activity is desirable to maximize the tumour radiation dose yet avoid severe myelotoxicity. Recently, the European Association of Nuclear Medicine (EANM) published a standard operational procedure (SOP) for pre-therapeutic dosimetry in DTC patients incorporating a safety threshold of a 2 Gy absorbed dose to the blood as a surrogate for the red marrow. We sought to evaluate the safety and effectiveness in everyday tertiary referral centre practice of treating advanced DTC with high 131 I activities chosen primarily based on the results of dosimetry following this SOP. We retrospectively assessed toxicity as well as biochemical and scintigraphic response in our first ten patients receiving such therapy for advanced DTC. The 10 patients received a total of 13 dosimetrically guided treatments with a median administered activity of 14.0 GBq (range: 7.0-21.4 GBq) 131 I. After 6 of 13 treatments in 6 of 10 patients, short-term side effects of 131 I therapy, namely nausea, vomiting or sialadenitis, were observed. Leukocyte and platelet counts dropped significantly in the weeks after 131 I treatment, but returned to pre-treatment levels by 3 months post-therapy. Serum thyroglobulin levels decreased after 12 of 13 treatments (median reduction: 58%) in 9 of 10 patients. In our initial patient cohort, high-activity 131 I therapy for advanced DTC based on pre-therapeutic blood dosimetry following the EANM SOP was safe and well tolerated. Such treatment almost always produced a partial biochemical tumour response. (orig.)

A set of portable radioisotopic control and measuring instruments

International Nuclear Information System (INIS)

Pospeev, V.V.; Sidorov, V.N.; Tesnavs, Eh.R.; Uleksin, V.I.

1979-01-01

The problems and perspectives are examined of the portable radioisotope instruments application in agriculture, building industry, engeeniring and geological survay and in melioration. Principles are given of creation a series of radioisotopic instruments based on the principle of ganging. The series described consists of radioisotopic densimeters and moisture gages of the portable type, based on the ganging principle. The instruments differ in the measuring converters and have unified information processing and power supply devices. Criteria are stated for the ganging principle estimation, in particular, estimation of the technical means' compatibility. Four different types of compatibility are distinguished: an information compatibility; a metrological compatibility; structural and operational compatibility. Description is given of the unified information processing device - the unified pulse counter of the SIP-1M type and description of a row of radioisotopic measuring converters, which provides a possibility for completing the portable radioisotope densimeter of the RPP-2 type, intended for measuring densities of concrets and soils in the surface layer up to 30 cm and the density range from 1000 to 2500 kg/m 3 ; portable radioisotope densimeter of the RPP-1 type having measuring range from 600 to 1500 kg/m 3 ; surface-depth radioisotopic densimeter of the PPGR-1 type and surface-depth radioisotopic moisture gage of the VPGR-1 type [ru

Radioisotopic indicators in microbiology

International Nuclear Information System (INIS)

Isamov, N.N.

1976-01-01

The book comprises data obtained by the laboratory of radiobiology (Uzbek Research Veterinary Institute) for 15 years and sums up data of domestic and foreign scientists; it discusses problems of the utilization of radioactive isotopes of sulphur, cadmium, phosphorus and other chemical elements by microorganisms; indicates the specificity of the utilization of radioisotopes in microbiology. The influence is considered of external factors on the inclusion of radioisotopes into microorganisms, methods are discussed of obtaining labelled microorganisms and their antigens, radioactivity of bacteria is considered as affected by the consistency and composition of the nutritive medium and other problems

Abstracts of the third conference on radioisotopes and their applications

International Nuclear Information System (INIS)

2002-10-01

The Third Uzbekistan Conference on radioisotopes and their applications was held on 8-10 October, 2002 in Tashkent, Uzbekistan. The specialists discussed various aspects of modern problems of radiochemistry, radioisotope production, technology of radioisotopes and compounds, activations analysis applications, radionuclides, radioimmunoassays, application of radioisotopes in industry, medicine, biology and agriculture. More than 80 talks were presented in the meeting

CsPbBr{sub 3} nanocrystal saturable absorber for mode-locking ytterbium fiber laser

Energy Technology Data Exchange (ETDEWEB)

Zhou, Yan; Li, Yue; Xu, Jianqiu; Tang, Yulong, E-mail: yulong@sjtu.edu.cn [Key Laboratory for Laser Plasmas (MOE), Department of Physics and Astronomy, Collaborative Innovation Center of IFSA, Shanghai Jiao Tong University, Shanghai 200240 (China); Hu, Zhiping; Tang, Xiaosheng [Key Laboratory of Optoelectronic Technology and Systems of the Education Ministry of China, College of Optoelectronic Engineering, Chongqing University, Chongqing 400044 (China)

2016-06-27

Cesium lead halide perovskite nanocrystals (CsPbX{sub 3}, X = Cl, Br, I) have been reported as efficient light-harvesting and light-emitting semiconductor materials, but their nonlinear optical properties have been seldom touched upon. In this paper, we prepare layered CsPbBr{sub 3} nanocrystal films and characterize their physical properties. Broadband linear absorption from ∼0.8 to over 2.2 μm and nonlinear optical absorption at the 1-μm wavelength region are measured. The CsPbBr{sub 3} saturable absorber (SA), manufactured by drop-casting of colloidal CsPbBr{sub 3} liquid solution on a gold mirror, shows modulation depth and saturation intensity of 13.1% and 10.7 MW/cm{sup 2}, respectively. With this SA, mode-locking operation of a polarization-maintained ytterbium fiber laser produces single pulses with duration of ∼216 ps, maximum average output power of 10.5 mW, and the laser spectrum is centered at ∼1076 nm. This work shows that CsPbBr{sub 3} films can be efficient SA candidates for fiber lasers and also have great potential to become broadband linear and nonlinear optical materials for photonics and optoelectronics.

Studies of radioisotope production with an AVF cyclotron in TIARA

Energy Technology Data Exchange (ETDEWEB)

Sekine, Toshiaki [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

1997-03-01

The production of radioisotopes to be used mainly for nuclear medicine and biology is studied with an AVF cyclotron in TIARA. A production method of no-carrier-added {sup 186}Re with the {sup 186}W(p,n){sup 186}Re reaction has been developed; this product may be used as a therapeutic agent in radioimmunotherapy due to the adequate nuclear and chemical properties. For the study of the function of plants using a positron-emitter two-dimensional imaging system, a simple method of producing the positron emitter {sup 18}F in water was developed by taking advantage of a highly-energetic {alpha} beam from the AVF cyclotron. (author)

Micronucleus induction as a measure of I-131 exposure

Energy Technology Data Exchange (ETDEWEB)

Kasuba, V; Horvat, D [Inst. for Medical Recearch and Occupational Health, Zagreb (Croatia). Laboratory for Mutagenesis; Kusic, Z [Clinical Hospital Sestre Milosrdnice, Zagreb (Croatia). Dept. of Oncology and Nuclear Medicine; Vlatkovic, M [Clinical Hospital Centre, Zagreb (Croatia). Dept. of Nuclear Medicine and Radiation Protection

1994-10-01

The change of cell numbers in the peripheral blood following irradiation has been studied for many years, particularly in patients undergoing radiotherapy. Recently, attention is directed towards the use of cytogenetic-mutagenetic methods to estimate the biological effects of received radiation dose. The aim of our study was to identify the difference in number and distribution of micronucleus, depending of applied therapeutic dose of iodine-131. According to their diagnosis, six patients have received iodine-131 in range from 80 to 140 mCi, while in the other group of patients the dose values varied from 7 to 32 mCi. On in vitro peripheral blood lymphocyte cultures micronucleus test was applied. Micronucleus analyses were carried out before the treatment, 24, 48 and 96 hours after the oral application of radiopharmaceutical. The number of micronucleus is showing increase, depending on applied radioactivity of iodine-131 and duration of exposition. The clear dose response relationship was never found. These results illustrate the problem associated with the inhomogeneous distribution of dose which results from the concentration of incorporated radionuclide into thyroid or other tissues. (author).

Computerized control system for administration of the radioisotope use

International Nuclear Information System (INIS)

Sago, Tsutomu; Ito, Shin; Isozumi, Yasuhito; Kurihara, Norio

1986-01-01

An on-line computer system for administration of the radioisotope use has been developed. This system consists of a multi-job type host computer and two sets of personal computers with identification card-readers. The personal computers are employed as terminal devices for radioisotope users. By the use of an identification card, entrance and leaving times are recorded automatically. Furthermore, an easy operation of the personal computer permits users to access to the information of their resistered radioisotopes, such as nuclides, chemical forms, updated activities, storage locations, and history of usage. A recording sheet on which those data are printed is provided from the personal computer. After the use of radioisotopes, users can record their data on the recording sheets. These records are used as the input data to this system to update the data of the used radioisotopes. Owing to the concise format of the recording sheet and various sorting programs developed in present work, this system enables us to grasp the exact flow of the radioisotopes from purchase to disposal. Out-put data from high-speed kanji printer can provide many important books which are legally requested to be kept for administration of the radioisotope use. (author)

The production and application of radioisotopes

International Nuclear Information System (INIS)

O'Neill, W.P.; Evans, D.J.R.

1987-01-01

This paper outlines the historical evolution of radioisotopes from first concepts and discoveries to significant milestones in their production and the development of applications throughout the world. Regarding production, it addresses the methods that have been used at various stages during this evolution outlining the important findings that have led to further developments. With respect to radioisotope applications, the paper addresses the development of markets in industry, medicine, and agriculture and comments on the size of these markets and their rate of growth. Throughout, the paper highlights the Canadian experience and it also presents a Canadian view of emerging prospects and a forecast of how the future for radioisotopes might develop. (author)

Historical variations of Bera Lake (Malaysia) sediments geochemistry using radioisotopes and sediment quality indices

International Nuclear Information System (INIS)

Mohammadreza Gharibreza; John Kuna Raj; Ismail Yusoff; Zainudin Othman; Wan Zakaria Wan Muhamad Tahir; Muhammad Aqeel Ashraf

2013-01-01

The Bera Lake basin is a lacustrine mire system and the largest natural lake in Peninsular Malaysia. Three cores were collected from the lake sediments in order to assess sediment quality and ecological risks for aquatic life and human health. An index analysis approach (C f , C d , E r , and IR) and fallout 210 Pb and 137 Cs radioisotopes were applied to assess the impacts of environmental evolutionary changes. Sediment chronology was determined using the Constant Rate of Supply model with the resultant ages verified by 137 Cs horizons. Although the general contamination factors indicate low risk conditions in Bera Lake the risks associated with individual layers ranged from moderate to considerable. Five deforestation phases can be identified in the dated sediment cores with distinct variations in heavy metal influxes since 1972. These phases are in excellent agreement with the dates of land clearance and development projects undertaken over the past four decades. This study has highlighted the capability of contamination factors and chronological methods in environmental evolutionary studies where catchments have experienced extensive land use changes. The destiny of heavy metal influxes into a lake can also be revealed using this methodology. (author)

Twenty years of Korea radioisotope association history

International Nuclear Information System (INIS)

2005-09-01

This contents has two parts. The first part describes the present and post of Korea radioisotope association which are about the foundation of the association, organization, main projects and vision of the association. The second part is about the use and the prospect of radiation and radioisotope in Korea, which shows the plan of expansion of use of radiation and radioisotope, the prospect and present condition in fields such as medical, industry and farming, product and distribution, research and development of human resources, system and management of safety of radiation.

X-ray application in diagnostics and therapeutics

International Nuclear Information System (INIS)

Braun, H.

1975-01-01

The lecture gives a general survey on the present possibilities of application of X-rays and radio-isotopes in medical diagnostics and therapeutics. The possibility of decreasing the radiation exposure by using image intensifiers and television is particularly indicated. The advantages of scintiscanning in diagnostics are presented by means of a series of examples. The increasing significance of telecurie equipment and particle accelerators are refered to in therapeutics. Finally, the radiation risk due to the medical application of radiation to the patient and the personnel is discussed and compared to the natural radiation exposure. (ORU/LH) [de

Integro-differential equation analysis and radioisotope imaging systems. Research proposal. [Testing of radioisotope imaging system in phantoms

Energy Technology Data Exchange (ETDEWEB)

Hart, H.

1976-03-09

Design modifications of a five-probe focusing collimator coincidence radioisotope scanning system are described. Clinical applications of the system were tested in phantoms using radioisotopes with short biological half-lives, including /sup 75/Se, /sup 192/Ir, /sup 43/K, /sup 130/I, and /sup 82/Br. Data processing methods are also described. (CH)

Abstracts of the second conference on radioisotopes and their applications

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-10-01

The Second Uzbekistan Conference on radioisotopes and their applications was held on 3-5 October, 2000 in Tashkent, Uzbekistan. The specialists discussed various aspects of modern problems of radiochemistry, radioisotope production, technology of radioisotopes and compounds, activations analysis applications, radionuclides, radioimmunoassays, application of radioisotopes in industry, medicine, biology and agriculture. More than 80 talks were presented in the meeting. (A.A.D.)

One-year, regional-scale simulation of {sup 137}Cs radioactivity in the ocean following the Fukushima Dai-ichi Nuclear Power Plant accident

Energy Technology Data Exchange (ETDEWEB)

Tsumune, D.; Tsubono, T.; Misumi, K.; Maeda, Y.; Yoshida, Y.; Hayami, H. [Central Research Institute of Electric Power Industry, Chiba (Japan). Environmental Science Research Lab.; Aoyama, M. [Meteorological Research Institute, Tsukuba (Japan); Uematsu, M. [The Univ. of Tokyo, Chiba (Japan). Atmosphere and Ocean Research Inst.

2013-07-01

A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant following the Great East Japan Earthquake and tsunami of 11 March 2011 resulted in the release of radioactive materials to the ocean by two major pathways: direct release from the accident site and atmospheric deposition. A 1 yr, regional-scale simulation of {sup 137}Cs activity in the ocean offshore of Fukushima was carried out, the sources of radioactivity being direct release, atmospheric deposition, and the inflow of {sup 137}Cs deposited into the ocean by atmospheric deposition outside the domain of the model. Direct releases of {sup 137}Cs were estimated for 1 yr after the accident by comparing simulated results and measured activities adjacent to the accident site. The contributions of each source were estimated by analysis of {sup 131}I/{sup 137}Cs and {sup 134}Cs/{sup 137}Cs activity ratios and comparisons between simulated results and measured activities of {sup 137}Cs. The estimated total amounts of directly released {sup 131}I, {sup 137}Cs, and {sup 137}Cs were 11.1 ± 2.2 PBq, 3.5 ± 0.7 PBq, and 3.6 ± 0.7 PBq, respectively. Simulated {sup 137}Cs activities attributable to direct release were in good agreement with measured {sup 137}Cs activities not only adjacent to the accident site, but also in a wide area in the model domain, therefore this implies that the estimated direct release rate was reasonable. Employment of improved nudging data by JCOPE2 improved both the offshore transport result and the reproducibility of {sup 137}Cs activities 30 km offshore. On the other hand, simulated {sup 137}Cs activities attributable to atmospheric deposition were low compared to measured activities. The rate of atmospheric deposition into the ocean was underestimated because of a lack of measurements of deposition into the ocean when atmospheric deposition rates were being estimated. Simulated {sup 137}Cs activities attributable to the inflow of {sup 137}Cs deposited into the ocean outside the

Radioisotope production by reactors and cyclotrons in Japan

International Nuclear Information System (INIS)

Murakami, Yukio

1978-01-01

Present status of radioisotope production in Japan and the increasing demand from various fields are generally reviewed. Future problems associated with the shortage of economical supply are also discussed. The first half of this report is devoted to general review of the increasing demand for various radioisotopes from increasing number of users. The present status and future trends of the distribution of users of specific radioisotopes and their demands are shown. The remaining half of this report reviews the production with reactors and cyclotrons. The Japanese reactors producing radioisotopes are limited to low flux (10 13 ) research reactors at JAERI. Some problems associated with the improvement of availability and with the organizational structure are discussed. As for the production with cyclotrons, available facilities and the method of production are explained in detail. For clinical use, especially for the production of short lived radioisotopes, the advantage of a small special purpose cyclotron at each medical organization is emphasized. (Aoki, K.)

Biokinetic and therapeutic use of 131I-MIBG in nude mice hosting human neuroblastoma xenografts

International Nuclear Information System (INIS)

Laubenbacher, C.; Kriegel, H.; Moellenstaedt, S.; Senekowitsch, R.; Technische Univ. Muenchen

1988-01-01

The biological halflife of 131 I-MIBG in nude mice with xenotransplanted human neuroblastoma derived from the SK-N-SH cell line comes to 6 h. The adrenal gland and the neuroblastoma show the highest uptake of MIBG. Based on these datas it could be calculated that 185 MBq would be necessary to get 60 Gy radiation absorbed dose in the tumor. 15-20 days after injection of this activity the tumors could no longer be palpated and they remained missing over the whole observation period. 92.5 MBq weren't enough getting a stable remission. Eleven days p.i. neuroblastoma started growing again. For the first time it could be shown that only high activity of 131 I-MIBG is able to restrain neuroblastoma totally. (orig.)

Technical and economical availability of radioisotopes production in Brazil

International Nuclear Information System (INIS)

Lima, J.O.V.

1981-10-01

The technical and economical availability of radioisotopes production in Brazil by a low power research reactor, are done. The importance of radioisotope utilization and controled radiations, in areas such as medicine, industry and cost evaluation for the production in nuclear reactors. In the cost evaluation of a radioisotope production reactor, the studies developed by the Department of Nuclear Engineering of Universidade Federal de Minas Gerais - DEN/UFMG were used. The information analysis justify the technical and economical availability and the necessity of the radioisotopes production in Brazil. (E.G.) [pt

Surface Decontamination Studies of Cs-137 and Sr-85 Using Polymer Gel

International Nuclear Information System (INIS)

Pham, L.; Nguyen, C.; Nguyen, L.

2015-01-01

Strippable polymer coating is one of the methods for effective surface decontamination to remove isotopes on the contaminated surface. This method is applying in nuclear facilities on the World. In this paper, we present the results obtained in our laboratory from product the polymer coating to apply to remove radioisotopes of "1"3"7Cs and "8"5Sr from surface of glass, stainless steel, mild steel, ceramic, PVC plastic. This polymer gel solution consist of water soluble polymer preferably polyvinyl alcohol (PVA), plasticizing agent (glycerine) and chelating agents, (citric acid) which can be sprayed or pasted on to contaminated surface. After some hours, these gel solutions was dried to form a strong thin film and it was easily peeled off from a contaminated surface with the radioactive isotopes and can be disposed off as radioactive solid waste. In this study infrared spectrophotometry technique was used to examine the interaction of the cesium and strontium ions with polyvinyl alcohol (PVA), polymer gel and the results of the study were also presented. The results showed that decontamination efficiency of "1"3"7Cs and "8"5Sr strongly depended on property, porosity and smoothness of the contaminated surface and obtained from 95-99% on glass and stainless steel, ceramic and PVC plastic surfaces. The decontamination efficiency also depended on activity and coating thickness. Optimization of film thickness is around 0.2 mm. Decontamination efficiency of Polymer gel were compared with Decongel 1101 (product from USA) on surfaces. IR spectra studies indicated that Cs and Sr ions interacted with PVA and citric acid in Polymer gel through cacboxyl (C = O) group. Polymer gel could remove of "1"3"7Cs and "8"5Sr better than PVA gel does because of citric acid, which can form chelating complex with Cs and Sr ion. (author)

Development and application of industrial radioisotope instruments in China

International Nuclear Information System (INIS)

Lu Yanxiao

1994-09-01

Industrial radioisotope instruments are emerging as advanced monitoring, controlling and automation tools for industries in China. Especially the on-line analysis systems based on radioisotope instruments, referred to as nucleonic control systems (NCS), have more and more important role in the modernization and optimization of industrial processes. Over nearly four decades significant progress has been made in the development and application of radioisotope instruments in China. After a brief review of the history of radioisotope instruments, the state of the art of this kind of instruments and recent examples of their applications are given. Technical and economic benefits have resulted from the industrial applications of radioisotope instruments and the sales of products of their own in marketing. It is expected that along with the high speed growth of national economy, there will be greater demand for radioisotope instruments and nucleonic control systems in Chinese industry to promote the technological transformation and progress of traditional industries and to establish high-tech industries with technology-intensive products. Sustained efforts for the research and development of radioisotope instrument should be made to up-grade domestic instruments and to satisfy the needs of the smaller scale industries more common in China for low cost systems. (1 fig., 2 tabs.)

Differentiated thyroid cancer (papillary). Brain tumor metastasis as clinical onset. surgical treatment and "1"3"1I. 8 years disease-free

International Nuclear Information System (INIS)

Mena, D.; Pena, M.; Alvarez, L.; García del Rio, H.; Bruno, O.

2015-01-01

Introduction: The differentiated thyroid cancer is the most common endocrine neoplasia. The major manifestation belongs to the papillary variant (65-90%). The prognosis tends to be very favorable, with a mortality rate of 1.8 % and a disease-free rate up to 10 years of around 90-95 %. The distant metastasis in brain accounts for 0.1-5 %. There are no established protocols for the management of brain metastasis. Therapeutic options are: surgery, stereotactic radiotherapy / radiosurgery, and "1"3"1I. The successful management of this case is an option for brain metastasis from thyroid papillary carcinoma. Case report: A 77 year-old female begins with double vision (diplopia). She underwent twice a surgery for brain tumor with a histopathological report on thyroid papillary tissue. The endocrine evaluation determines euthyroid state except thyroglobulin (TG) 2300 ng/ml. Total thyroidectomy with classic thyroid papillary carcinoma. A diagnostic "1"3"1I scan after surgery shows for first time brain metastasis uptake. The patient receives 25 mCi of "1"3"1I as initial therapeutic dose, and subsequent therapeutic doses (50, 50, 75, 75, 50 mCi) in 2 years, in accordance with the evolution of magnetic resonance, clinic, endocrine lab, hematological analysis, and "1"3"1I scintigraphy, that shows the possible remission of the disease. The follow-up was carried out by means of a clinical control, thyroglobulin values, U.S., "1"3"1I scans, and magnetic resonance. The patient is at the present time over 11 years survival and 8 years disease-free. Discussion: Even though the distant metastasis is not very common in brain and is generally associated with aggressive variants of tumor, our case started with a metastatic brain tumor in an euthyroid patient with no thyroid pathology background and with low-risk post-thyroidectomy criterion. The "1"3"1I scan turned positive in brain metastasis when the patient was thyroidectomized. This detail must be considered important, since it

137Cs and 210Pb distribution in Manila Bay sediment

International Nuclear Information System (INIS)

Sta. Maria, Efren J.; Madrid, Jordan F.; Olivares, Ryan U.; Bulos, Adelina DM; Dayaon, Jennyvi P.; Asa, Anie Day DC; Sombrito, Elvira Z.

2011-01-01

Two radionuclides were measured in surface sediment samples taken from geographically distributed sections of Manila Bay, namely cesium-137 ( 137 Cs) and lead-210 ( 210 Pb). Results indicated a noticeable change in the radioactivity concentration levels in sediments collected in 2005 and 2010, with a median concentration of 1.0 and 2.64 Bq kg -1 , respectively. Higher levels of 137 Cs radioactivity were measured in the northern and inner portion of the bay adjacent to major river systems, agricultural and highly industrialized urban areas. 137 Cs isotope increased in activity in most of the samples especially in the northwestern areas of Bataan and Pampanga with five times more than the activity from the first sampling measurements. Nevertheless, radioactivity concentrations observed in surface sediments along the bay are within the range of radioactivity in several areas monitored in the Northern Hemisphere. The country has been frequented by tropical cyclones and storms that have caused erosion, which may have introduced elevated material input in the bay. In addition, wind-driven circulation especially in the shallower areas of the bay is a possibility for the substantial sediment movement and accumulation along this coast. Conversely, areas with higher 137 Cs have lower values of 210 Pb. In an undisturbed environment, 210 Pb deposition values are assumed nearly constant. Hence, changes in the radioactivity concentration levels of these radionuclides can be an indicator of pollution input from land-based sources, sediment movement and reworking in the coastal areas. At present, there is very limited information on the radioactivity level of various radioisotopes in Manila Bay.The data obtained are benchmark values against which changes that will be occurring in the bay can be assessed. (author)

Treatment of hyperthyroidism: use of 131I and 125I

International Nuclear Information System (INIS)

Atkins, H.L.

1977-01-01

Factors related to late hypothyroidism following the use of 131 I for treatment of hyperthyroidism are discussed with regard to age of patient, size of dose, previous surgery, immune status, and others. Possible reasons for the post-therapeutic hypothyroidism are discussed with regard to effects of radiation on the reproductive capacity of thyroid cells, effects of radiation on blood vessels, and dose distribution of radioiodine. The following therapeutic strategies are discussed: reduction of initial dose; multiple small doses; high dose radioiodine followed by replacement therapy; the use of external beam irradiation; and the use of 125 I

Molecular CsF 5 and CsF 2 +

KAUST Repository

Rogachev, Andrey Yu.; Miao, Mao-sheng; Merino, Gabriel; Hoffmann, Roald

2015-01-01

D5h star-like CsF5, formally isoelectronic with known XeF5− ion, is computed to be a local minimum on the potential energy surface of CsF5, surrounded by reasonably large activation energies for its exothermic decomposition to CsF+2 F2, or to CsF3 (three isomeric forms)+F2, or for rearrangement to a significantly more stable isomer, a classical Cs+ complex of F5−. Similarly the CsF2+ ion is computed to be metastable in two isomeric forms. In the more symmetrical structures of these molecules there is definite involvement in bonding of the formally core 5p levels of Cs.

Molecular CsF 5 and CsF 2 +

KAUST Repository

Rogachev, Andrey Yu.

2015-06-03

D5h star-like CsF5, formally isoelectronic with known XeF5− ion, is computed to be a local minimum on the potential energy surface of CsF5, surrounded by reasonably large activation energies for its exothermic decomposition to CsF+2 F2, or to CsF3 (three isomeric forms)+F2, or for rearrangement to a significantly more stable isomer, a classical Cs+ complex of F5−. Similarly the CsF2+ ion is computed to be metastable in two isomeric forms. In the more symmetrical structures of these molecules there is definite involvement in bonding of the formally core 5p levels of Cs.

RADIOISOTOPE INVENTORY FOR TSPA-SR

International Nuclear Information System (INIS)

Leigh, C.; Rechard, R.

2001-01-01

The total system performance assessment for site recommendation (TSPA-SR), on Yucca Mountain, as a site (if suitable) for disposal of radioactive waste, consists of several models. The Waste Form Degradation Model (i.e, source term) of the TSPA-SR, in turn, consists of several components. The Inventory Component, discussed here, defines the inventory of 26 radioisotopes for three representative waste categories: (1) commercial spent nuclear fuel (CSNF), (2) US Department of Energy (DOE) spent nuclear fuel (DSNF), and (3) high-level waste (HLW). These three categories are contained and disposed of in two types of waste packages (WPs)--CSNF WPs and co-disposal WPs, with the latter containing both DSNF and HLW. Three topics are summarized in this paper: first, the transport of radioisotopes evaluated in the past; second, the development of the inventory for the two WP types; and third, the selection of the most important radioisotopes to track in TSPA-SR

Results submitted to Bureau International des Poids et Mesures (BIPM) for international comparison on 134Cs activity

International Nuclear Information System (INIS)

Gibson, F.H.; Smith, L.V.; Rutledge, A.R.; Merritt, J.S.

1979-02-01

This report describes the equipment used and the results obtained by the Radioisotope Standardization Group in its participation in the international comparison of activity measurements of a 134 Cs solution that was sponsored by Bureau International des Poids et Mesures (BIPM). The 4π(PC)-γ coincidence method was used with the γ-channel gate set narrowly around photopeaks of approximately 800 keV. The results are compared with those from three other γ-channel gates. An assessment of known and suspected sources of uncertainty is included. (author)

Measurement of the Energy-Dependent Angular Response of the ARES Detector System and Application to Aerial Imaging

Science.gov (United States)

Joshi, Tenzing H. Y.; Quiter, Brian J.; Maltz, Jonathan S.; Bandstra, Mark S.; Haefner, Andrew; Eikmeier, Nicole; Wagner, Eric; Luke, Tanushree; Malchow, Russell; McCall, Karen

2017-07-01

The Airborne Radiological Enhanced-sensor System (ARES) includes a prototype helicopter-borne CsI(Na) detector array that has been developed as part of the DHS Domestic Nuclear Detection Office Advanced Technology Demonstration. The detector system geometry comprises two pairs of 23-detector arrays designed to function as active masks, providing additional angular resolution of measured gamma rays in the roll dimension. Experimental measurements, using five radioisotopes (137Cs, 60Co, 241Am, 131I, and 99mTc), were performed to map the detector response in both roll and pitch dimensions. This paper describes the acquisition and analysis of these characterization measurements, calculation of the angular response of the ARES system, and how this response function is used to improve aerial detection and localization of radiological and nuclear threat sources.

Assinatura da deposição atmosférica de testes nucleares em sedimentos da costa brasileira (240+239Pu e 137Cs

Directory of Open Access Journals (Sweden)

Christian J. Sanders

2012-01-01

Full Text Available The aim of this review is to take a look at Cold War era nuclear tests signatures found in Brazilian coastal sediments. Both137Cs and 240+239Pu signatures have been documented in mangrove, coastal mudflats and continental shelf sediments, associated with above ground nuclear tests beginning in the 1950's. The dates associated to the anthropogenic radionuclide signatures 137Cs and 240+239Pu along sediment columns are confirmed by 210Pb geochronology in many of the studies highlighted in this review. The results outlined in this review characterize the extent to which nuclear fallout products reach the Brazilian coast in quantities sufficient for detection, allowing the use of these radioisotopes as geochronometers.

Aspects of radioisotopes utilization in clinical medicine

International Nuclear Information System (INIS)

Rocha, A.F.G.; Lima e Forti, C.A. de; Cunha, M. da C.; Souza Maciel, O. de

1973-01-01

A revision concerning radioisotope use in Medicine have been dow. Harmless and effeciency of radioisotopes are shown. Techniques and advantages of tracers used for brain scintiscanning, lung scintiscanning, liver scintinscanning, spleen scintiscanning, bone scintiscanning and thyroid scintiscanning are described and images of them are presented [pt

Structure and manual of radioisotope-production data base, ISOP

International Nuclear Information System (INIS)

Hata, Kentaro; Terunuma, Kusuo

1994-02-01

We planned on collecting the information of radioisotope production which was obtained from research works and tasks at the Department of Radioisotopes in JAERI, and constructed a proto-type data base ISOP after discussion of the kinds and properties of the information available for radioisotope production. In this report the structure and the manual of ISOP are described. (author)

Radioisotopes in non-destructive testing

International Nuclear Information System (INIS)

Domanus, J.C.

1976-12-01

After defining nondestructive testing (NDT) and comparing this concept with destructive testing, a short description is given of NDT methods other than radiologic. The basic concepts of radiologic methods are discussed and the principles of radiography are explained. Radiation sources and gamma radiography machines are next reviewed and radiographic inspection of weldings and castings is described. A brief description is given of the radiographic darkroom and accessories. Other radioisotope methods, such as neutron radiography, are shortly reviewed. Cost estimations for radioisotopic equipment conclude the report. (author)

Radioisotopes: problems of responsibility arising from medicine