The gamma-ray lines of radionuclides, ordered by atomic and mass number

Erdtmann, G.; Soyka, W.

doi:10.1007/bf02524450

Cited by 25 publications

(5 citation statements)

References 2 publications

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“…RadPro utilizes mass attenuation coefficient data tabulated by Hubbel and Seltzer 9 and build‐up factors provided by the American Nuclear Society 10 and from Monte Carlo studies 11 . RadPro also incorporates the polyenergetic radionuclide spectra reported by Erdtmann and Soyka 12 . The NCRP 151 report provides TVL data for broad beam conditions as a function of photon energy, originating from Wachsmann and Drexler 13 as well as from the National Bureau of Standards 14 .…”

Section: Discussionmentioning

confidence: 99%

“…11 RadPro also incorporates the polyenergetic radionuclide spectra reported by Erdtmann and Soyka. 12 The NCRP 151 report provides TVL data for broad beam conditions as a function of photon energy, originating from Wachsmann and Drexler 13 as well as from the National Bureau of Standards. 14 Experimental measurements would be necessary as part of full implementation, but were beyond the scope of this feasibility study.…”

Section: Discussionmentioning

confidence: 99%

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Technical note: Investigating the suitability of existing facilities for a new Lu‐177 prostate‐specific membrane antigen therapy program

et al. 2023

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Background: 177 Lu prostate-specific membrane antigen (PSMA) therapy prolongs survival for some prostate cancer patients. To adopt this technique, institutions may need to evaluate the suitability of existing infrastructure. Purpose: Develop a methodology to determine whether existing facilities can accommodate a 177 Lu-PSMA therapy program. Methods: Room suitability is defined by both the ability to accommodate 177 Lu-PSMA therapy workflow and to provide appropriate radiation shielding. Two methods of shielding calculation were performed: (1) National Council on Radiation Protection and Measurements report 151 (NCRP-151), with workload defined in terms of the activity of 177 Lu administered, and (2) using the Rad-Pro shielding calculator. This methodology was applied to 131 I therapy, PET-CT uptake, PET-SPECT injection, and orthovoltage therapy rooms. Results: 131 I therapy rooms were found to meet both shielding and workflow requirements. The shielding was found to be adequate for orthovoltage and PET-SPECT facilities, neglecting patient transit between external washrooms. The workflow was the limiting factor for these rooms due to the requirement of dedicated washrooms that shield the patient and contain possible contamination. The PET-CT facility did not meet either criteria. The NCRP-151 method generally predicted a higher dose rate on the other side of shielding than did the RadPro calculator. The dose rate on the other side of concrete shielding as predicted by the NCRP-151 method increased relative to the dose rate predicted by the RadPro calculator as shielding thickness increased. For lead shielding, the dose rate predicted by the NCRP-151 method decreased relative to the result predicted by the RadPro calculator with increasing material thickness. Conclusions: 131 I therapy, PET-CT uptake, PET-SPECT injection, and orthovoltage therapy rooms were considered. The 131 I treatment rooms were the best candidate for 177 Lu-PSMA therapy, due to their shielding and capability to accommodate the necessary workflow.

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Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Technical note: Investigating the suitability of existing facilities for a new Lu‐177 prostate‐specific membrane antigen therapy program

et al. 2023

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“…Casaccia-ENEA. About 0.5 g of each sample was irradiated in the rotatory rack, Lazy Susan, at 2.6 × 10 12 n×cm 2 ×s −1 for 12 h. Table 2 shows the radioisotopes used to calculate the concentration of the analyzed elements along with the nuclear data and the relative gamma-spectrometry interferences [35][36][37].…”

Section: Inorganic Fractionmentioning

confidence: 99%

Halogenated Volatile Organic Compounds in Water Samples and Inorganic Elements Levels in Ores for Characterizing a High Anthropogenic Polluted Area in the Northern Latium Region (Italy)

Russo

Notardonato

Rosada

et al. 2021

IJERPH

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This paper shows a characterization of the organic and inorganic fraction of river waters (Tiber and Marta) and ores/soil samples collected in the Northern Latium region of Italy for evaluating the anthropogenic/natural source contribution to the environmental pollution of this area. For organic compounds, organochloride volatile compounds in Tiber and Marta rivers were analyzed by two different clean-up methods (i.e., liquid–liquid extraction and static headspace) followed by gas chromatography–electron capture detector (GC-ECD) analysis. The results show very high concentrations of bromoform (up to 1.82 and 3.2 µg L−1 in Tiber and Marta rivers, respectively), due to the presence of greenhouse crops, and of chloroform and tetrachloroethene, due to the presence of handicrafts installations. For the qualitative and quantitative assessment of the inorganic fraction, it is highlighted the use of a nuclear analytical method, instrumental neutron activation analysis, which allows having more information as possible from the sample without performing any chemical-physical pretreatment. The results have evidenced high levels of mercury (mean value 88.6 µg g−1), antimony (77.7 µg g−1), strontium (12,039 µg g−1) and zinc (103 µg g−1), whereas rare earth elements show levels similar to the literature data. Particular consideration is drawn for arsenic (414 µg g−1): the levels found in this paper (ranging between 1 and 5100 µg g−1) explain the high content of such element (as arsenates) in the aquifer, a big issue in this area.

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“…TABELA 9 -Fotopicos das impurezas radionuclídicas com suas principais energias [37,92,93] . [90] é de 10 µg/mL e o da Européia [91] 20 µg/mL.…”

Section: Radionuclídeo Limiteunclassified

“…43, mostra os radionuclídeos encontrados no gel de MoZr préformado (L1 e P) e irradiado. O gel pós-formado L2 teve como única impureza o TABELA 43 -Radionuclídeos [92,93] NIETO [37,42] identificou os radionuclídeos 175 Hf, 95 Zr, 95 Nb e 181 Hf na irradiação do gel de MoZr do tipo pré-formado. Segundo a autora as impurezas são provenientes da ativação do Mo, Zr e impurezas químicas dos compostos usados.…”

Section: Pureza Radionuclídicaunclassified

Estudos de técnicas de concentração da atividade de 99mTc eluído de geradores de 99Mo/99mTc tipo gel

Suzuki¹

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On average 80% of the radiopharmaceuticals used in Nuclear Medicine are labeled with 99m Tc due to its physical properties and easy attainment through of 99 Mo/ 99m Tc generators. The Directory of Radiopharmacy (DIRF) of IPEN-CNEN/SP developed a gel type chromatographic generator of MoZr with 99 Mo produced by 98 Mo(n,γ) 99 Mo reaction that occurs at the IEA-R1 Nuclear Reactor. The gel is composed of zirconium molibdate with elution volume of 12 mL with an activity of 11100 MBq (300 mCi) producing a radioactive concentration of 925 MBq (25 mCi)/mL. The fission generator gives a higher radioactive concentration around 1850 MBq (50 mCi)/mL. The aim of this work is to study a system of post-elution concentration of 99m Tc for the attainment of a high enough radioactive concentration to meet the demands of the market, with a proved quality. Two types of systems of post-elution concentration were developed: the single and the tandem. The most appropriate system for the gel generator of 99 Mo/ 99m Tc, being at the same time sterile and vacuum automated, was the tandem system using Dionex 2.5 cc/QMA cartridges. The gel generator is eluted with 10 mL of solution of 0.1% NaCl and the pertechnetate anion is retained in the QMA cartridge and further eluted with 4 mL of saline. The process takes no more than 30 minutes. The elution efficiency of the system of concentration was 90 %. At the beginning of 2009 a global crisis in the supply of 99 Mo took place making it necessary the development of alternative technologies for the production of 99 Mo/ 99m Tc generators using fission produced 99 Mo and the development of an appropriate method to extend the useful life of this generator. The results of this study showed that the same system developed for the post-concentration of the gel generator can be employed for the fission generator, using the tandem system, giving a concentration factor of 3 for the elution of 99m Tc. LISTA DE FIGURAS FIGURA 1 Curva de decaimento e crescimento do gerador de 99 Mo/ 99m Tc

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The gamma-ray lines of radionuclides, ordered by atomic and mass number

Cited by 25 publications

References 2 publications

Technical note: Investigating the suitability of existing facilities for a new Lu‐177 prostate‐specific membrane antigen therapy program

Technical note: Investigating the suitability of existing facilities for a new Lu‐177 prostate‐specific membrane antigen therapy program

Halogenated Volatile Organic Compounds in Water Samples and Inorganic Elements Levels in Ores for Characterizing a High Anthropogenic Polluted Area in the Northern Latium Region (Italy)

Estudos de técnicas de concentração da atividade de 99mTc eluído de geradores de 99Mo/99mTc tipo gel

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