Perspectives on research reactor utilization

Dodd, Brian; Dolan, Thomas J.; Laraia, Michele; Ritchie, I.G.

doi:10.1016/s0921-4526(01)01055-9

Cited by 19 publications

(6 citation statements)

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“…Nowadays the majority of the world's largeand medium-scale routine production is carried out mainly at five major ageing research reactors, most of them commissioned more than 50 years ago (Dodd 2002, Krijger 2013. Due to unexpected outages or planned reactor shutdowns, significant 99m Tc shortages on the international market have already occurred in recent years (2009/2010).…”

Section: Introductionmentioning

confidence: 99%

“…Due to unexpected outages or planned reactor shutdowns, significant 99m Tc shortages on the international market have already occurred in recent years (2009/2010). This fact, along with the forthcoming permanent shutdown planned for some of the reactors concerned, has prompted at global scale the search for alternative non-HEU-based 99m Tc production routes (IAEA 2013, Dodd et al 2002, Krijger et al 2013, NEA 2017).…”

Section: Introductionmentioning

confidence: 99%

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Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction

et al. 2018

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Evaluation of the radioisotopic purity of technetium-99m (Tc) produced in GBq amounts by proton bombardment of enriched molibdenum-100 (Mo) metallic targets at low proton energies (i.e. within 15-20 MeV) is conducted. This energy range was chosen since it is easily achievable by many conventional medical cyclotrons already available in the nuclear medicine departments of hospitals. The main motivation for such a study is in the framework of the research activities at the international level that have been conducted over the last few years to develop alternative production routes for the most widespread radioisotope used in medical imaging. The analysis of technetium isotopes and isomeric states (Tc) present in the pertechnetate saline NaTcO solutions, obtained after the extraction/purification procedure, reveals radionuclidic purity levels basically in compliance with the limits recently issued by European Pharmacopoeia 9.3 (2018 Sodium pertechnetate (Tc) injection 4801-3). Moreover, the impact of Tc contaminant nuclides on the final image quality is thoroughly evaluated, analyzing the emitted high-energy gamma rays and their influence on the image quality. The spatial resolution of images from cyclotron-producedTc acquired with a mini-gamma camera was determined and compared with that obtained using technetium-99m solutions eluted from standard Mo/Tc generators. The effect of the increased image background contribution due to Compton-scattered higher-energy gamma rays (E > 200 keV), which could cause image-contrast deterioration, was also studied. It is concluded that, due to the high radionuclidic purity of cyclotron-produced Tc usingMo(p,2n)Tc reaction at a proton beam energy in the range 15.7-19.4 MeV, the resulting image properties are well comparable with those from the generator-eluted Tc.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction

et al. 2018

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“…In research reactors, creating a neutron beam line is usually done using a beam tube. The beam tube is generally a steel or aluminum tube that is installed inside the biological shield of the reactor, which is water and concrete, and by creating an air column between the reactor core and outside the biological shield, it permits neutrons and gamma to transport out of the biological shield [11]. In other words, beam tubes provide external irradiation facilities.…”

Section: Introductionmentioning

confidence: 99%

Feasibility study on PGNAA experiments using a prototype neutron beam at Isfahan MNSR

et al. 2023

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In this study, the feasibility study of Prompt Gamma Neutron Activation Analysis (PGNAA) experiments at Isfahan Miniature Neutron Source Reactor (MNSR) has been done using a prototype neutron beam. This neutron beam was not originally created for this purpose, but previous studies on this neutron beam have shown that it has enough neutron flux to carry out some irradiations outside the reactor core. This prototype neutron beam provided a neutron flux of order 105 n·cm-2·s-1 and a circular diameter of 5 cm for the experiments. In addition, an appropriate setup for High Purity Germanium detector (HPGe) was done at the beam outlet, where the sample is irradiated. A simple shield was also installed to prevent radiation damage to the detector. Experiments were conducted for bulk samples of salt solution with different concentrations and the prompt gamma spectrums have been obtained and analyzed.

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“…This limit on enrichment is considered to be an isotopic barrier for weapon usability. To develop the technology required using LEU instead of HEU in research and test reactors, Department of Energy (DOE) USA established the Reduced Enrichment Research and Test Reactor (RERTR) program in 1978 at the Argonne National Laboratory (ANL) (Travelli, 1996;Dodd et al, 2002). In order to provide guidelines and facilitate the reactor conversion from HEU to LEU fuel, the IAEA devised a standard benchmark material test reactor (MTR) (IAEA-TECDOC-233, 1980).…”

Section: Introductionmentioning

confidence: 99%

Calculation of fuel burnup and radionuclide inventory in the 10MW MTR type research reactor using the GETERA code

Dawahra

Khattab

Saba

2015

Annals of Nuclear Energy

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Perspectives on research reactor utilization

Cited by 19 publications

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Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction

Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction

Feasibility study on PGNAA experiments using a prototype neutron beam at Isfahan MNSR

Calculation of fuel burnup and radionuclide inventory in the 10MW MTR type research reactor using the GETERA code

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Perspectives on research reactor utilization

Cited by 19 publications

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Radioisotopic purity and imaging properties of cyclotron-produced 99mTc using direct 100Mo(p,2n) reaction

Radioisotopic purity and imaging properties of cyclotron-produced 99mTc using direct 100Mo(p,2n) reaction

Feasibility study on PGNAA experiments using a prototype neutron beam at Isfahan MNSR

Calculation of fuel burnup and radionuclide inventory in the 10MW MTR type research reactor using the GETERA code

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Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction

Radioisotopic purity and imaging properties of cyclotron-produced ^99mTc using direct ¹⁰⁰Mo(p,2n) reaction