scholarly journals 68Ge/68Ga-generator: a radionuclide source or an approved drug?

2021 ◽  
Vol 96-97 ◽  
pp. S100
Author(s):  
Herbert Kvaternik ◽  
Elisabeth Plhak ◽  
Daniel Paul ◽  
Bernhard Rumpf ◽  
Reingard Aigner
Keyword(s):  
Radionuclide Source

crease the proportion of machine sources in the near future. If radiation process­ ing continues to grow, the shortage of Co, which has caused some delays in deliveries in the past, will become more acute. This also points to an increasingly important role for electron accelerators. Generalizing conclusions about the relative economics of different types of irradiation may be misleading because the relative costs of different radiation facilities are considerably affected by local conditions such as costs of electricity, labor, transportation, and construction. The economics of operation also depends on the use level of a facility. Where operations can be continued day and night for months a year a radionuclide source may be more economic, however, where intermittent operations are more likely a machine source may be more advanta­ geous. Sociopolitical considerations relate to the observation that in some countries it is getting more and more difficult to overcome local opposition to the installation of new radioisotope sources. Fears for the safety of the environment in shipping and storing large inventories of 60Co or 137Cs are often cited as the main reason for this opposition. Regardless of whether these fears are justified, planners cannot disregard them. As an example, the National Food Processors Association (NFPA), with support from the U.S. Department of Energy, negotiated in the summer of 1985 for a site in Dublin, California, to build a demonstration and training facility for food irradiation, using 3 million Ci of ,Cs. The opposition

1995 ◽  
pp. 45-45
Keyword(s):  
Department Of Energy ◽  
Food Irradiation ◽  
Local Conditions ◽  
Electron Accelerators ◽  
Local Opposition ◽  
A Site ◽  
Near Future ◽  
And Training ◽  
Radionuclide Source ◽  
The U.S

scholarly journals Monte Carlo simulation study on the 241Am-Be radionuclide source reference neutron radiation

2020 ◽  
Vol 35 (4) ◽  
pp. 283-293
Author(s):  
Yixin Liu ◽  
Song Zhang ◽  
Yikun Qian ◽  
Yuchen Huang ◽  
Benjiang Mao ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Free Field ◽  
Neutron Radiation ◽  
Neutron Energy Spectrum ◽  
Measurement Instruments ◽  
Dose Equivalent ◽  
Monte Carlo Simulation Study ◽  
Neutron Measurement ◽  
Radionuclide Source

In order to study the feasibility of using lightweight 241Am-Be radionuclide reference neutron radiation field for the calibration of neutron measurement instruments, this paper reported the Monte Carlo simulation work on free field reference neutron radiation, standard reference neutron radiation regulated by ISO-8529 series standards and minitype reference neutron radiation we designed. The distributions of dose equivalent rates and neutron energy spectrum in different conditions, such as different room types, different room sizes and different shield materials were the main simulation contents for analyzing the characteristics of the three types of reference neutron radiation. According to the simulation results, theoretical supports were provided for the discussion on the minitype reference neutron radiation for calibration purpose.

scholarly journals Quality Assurance with Dosimetric Consistency of a Co-60 Teletherapy Unit

2017 ◽  
Vol 4 (1) ◽  
pp. 88
Author(s):  
Num Prasad Acharya ◽  
Tika Ram Lamichhane ◽  
Bidyapati Jha
Keyword(s):  
Quality Assurance ◽  
Dose Rate ◽  
Radiation Treatment ◽  
Standard Dose ◽  
Dose Delivery ◽  
Radiation Hazards ◽  
Average Output ◽  
Energy Agency ◽  
Actual Output ◽  
Radionuclide Source

<p class="Default">It is essential to know the standard dose rate, output of Co-60 source in the radiation treatment periodically. It is because the over dosage may cause radiation hazards where as under dosage may lead to unsatisfactory treatment of cancer. Present study focused on the radiation standards and dosimetry for the assurance of the quality and verify that the output of the ionizing radiation emitting medical instruments such as Teletherapy Unit (TTU) which should be within ±2% of the stated one. Present study was done as a part of the regularity of quality assurance (QA) of telecobalt radiotherapy unit that includes the dosimetric measurements of Co-60 TTU at Bhaktapur Cancer Hospital (BCH), Bhaktapur per each month from 29 March 2012 to 29 December 2014. The radionuclide source is Co-60 which has been incorporated in TTU, BCH for the purpose of therapeutic treatment of cancer. The Co-60 source decays continuously to Ni-60 (half-life of 5.27 years) with the decrease in its activity and hence the output dose rate. The calculations of actual dose rate of Co-60 TTU were done by the source to surface distance (SSD) technique. It has been concluded that there is a quality assurance management in Co-60 TTU, BCH with the consistency in the average output dose rate obtained by the actual dosimetry values and the expected output values obtained by decay method. The values obtained by actual dosimetry are within ±2% of the expected values so that the deviation of the actual output dose rate from the expected output data lies within the permissible limit as prescribed by International Atomic Energy Agency (IAEA) and International Commission on Radiation Units and Measurement (ICRUM). In conclusion, our study shows a trend towards uniform and better dose delivery from Co-60 TTU, BCH, Nepal</p><p><strong>Journal of Nepal Physical Society</strong><em><br /></em>Volume 4, Issue 1, February 2017, Page: 88-92</p>

Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material

2004 ◽  
Vol 92 (9-11) ◽  
Author(s):  
Volker Metz ◽  
W. Schüßler ◽  
B. Kienzler ◽  
Thomas Fanghänel
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Source Term ◽  
Geochemical Modeling ◽  
Test Site ◽  
Radioactive Waste Disposal ◽  
Salt Mine ◽  
Waste Forms ◽  
Radionuclide Inventory ◽  
Radionuclide Source

SummaryThe Asse salt mine was used as a test site for radioactive waste disposal from 1967 to 1978. Low- and intermediate-level waste forms (LLW/ILW) were emplaced, containing a total radionuclide inventory of 3×10Geochemical modeling leads to the conclusion that Portland cement, a Mg(OH)

The kerma-constant and kerma-equivalent of a radionuclide source

1985 ◽  
Vol 58 (4) ◽  
pp. 300-304 ◽  
Author(s):  
V. P. Mashkovich
Keyword(s):  
Radionuclide Source

Compliance Assessments of Hypothetical Geological Nuclear Waste Isolation Systems with the Draft Epa Standard

1982 ◽  
Vol 15 ◽  
Author(s):  
M. D. Siegel ◽  
M. S. Chu ◽  
R. E. Pepping
Keyword(s):  
Contaminant Transport ◽  
Nuclear Waste ◽  
Department Of Energy ◽  
Mathematical Treatment ◽  
Mixing Processes ◽  
Several Variables ◽  
Isolation Systems ◽  
Technical Basis ◽  
Radionuclide Source

Estimates of potential radionuclide releases from HLW storage facilities in geologic formations are an integral part of the technical basis for the regulation of nuclear waste disposal. We have attempted to assess the importance of the variation of several variables and model assumptions to the calculation of radionuclide discharge from hypothetical repositories. The conceptual models of the repository sites are consistent with our current understanding of the characteristics of the geologic environments being studied by the Department of Energy. It must be stressed that we have not attempted to accurately model any real sites; at the present time, the available data are not sufficient for this purpose. Large uncertainties exist in the characterization of the solubilities and sorption of radionuclides, in the description of the regional and local hydrogeology and in the mathematical treatment of contaminant transport in the presence of fracture flow and matrix diffusion. The fraction of waste that could be accessed by breaching the repository, the effects of mixing processes within the facility and the probability of human intrusion are not known. We have completed preliminary calculations of potential radionuclide discharges from hypothetical repositories in tuff and bedded salt [1,2]. Our theoretical approach and computational methods are illustrated in this paper with examples for a repository in volcanic tuff. We also briefly discuss the importance of radionuclide source term assumptions to the calculations for a bedded salt repository.

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