Design optimization and performances of New Sorgentina Fusion Source (NSFS) supporting materials research

Camprini, P. Console; Bernardi, D.; Pillon, M.; Angelone, M.; Frisoni, M.; Pietropaolo, A.; Pizzuto, A.; Agostini, P.

doi:10.1016/j.fusengdes.2015.04.031

Cited by 8 publications

(7 citation statements)

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“…The latter is an intense 14 MeV neutron source based on D-T fusion reactions thoroughly described in Refs . [14,15,16]. The nominal NSFS neutron emission rate, in continuous state, is about 4–5 × 10 15 s −1 , i.e., more than 104 times higher than the nominal value available at FNG.…”

Section: Resultsmentioning

confidence: 95%

“…In preparation of the experiment, we perform Monte Carlo (MC) simulations of the irradiation tests using the Fluka code [13]. The simulated experiment is benchmarked by experimental data, allowing the provision of quantitative predictions of the 99 Mo production by means of the New Sorgentina Fusion Source (NSFS) [14,15,16], a very intense 14 MeV D-T neutron source under investigation at ENEA, and currently in an advanced conceptual design stage. …”

Section: Introductionmentioning

confidence: 99%

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14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

et al. 2018

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Background: the gamma-emitting radionuclide Technetium-99m (99mTc) is still the workhorse of Single Photon Emission Computed Tomography (SPECT) as it is used worldwide for the diagnosis of a variety of phatological conditions. 99mTc is obtained from 99Mo/99mTc generators as pertechnetate ion, which is the ubiquitous starting material for the preparation of 99mTc radiopharmaceuticals. 99Mo in such generators is currently produced in nuclear fission reactors as a by-product of 235U fission. Here we investigated an alternative route for the production of 99Mo by irradiating a natural metallic molybdenum powder using a 14-MeV accelerator-driven neutron source. Methods: after irradiation, an efficient isolation and purification of the final 99mTc-pertechnetate was carried out by means of solvent extraction. Monte Carlo simulations allowed reliable predictions of 99Mo production rates for a newly designed 14-MeV neutron source (New Sorgentina Fusion Source). Results: in traceable metrological conditions, a level of radionuclidic purity consistent with accepted pharmaceutical quality standards, was achieved. Conclusions: we showed that this source, featuring a nominal neutron emission rate of about 1015 s−1, may potentially supply an appreciable fraction of the current 99Mo global demand. This study highlights that a robust and viable solution, alternative to nuclear fission reactors, can be accomplished to secure the long-term supply of 99Mo.

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Section: Resultsmentioning

confidence: 95%

Section: Introductionmentioning

confidence: 99%

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

et al. 2018

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“…While ENEA-FNG in its present configuration is well suited for testing physical processes related to radioisotopes production by means of inelastic neutron reactions involving 14 MeV fusion, a 14 MeV neutron source featuring a higher neutron emission rate (above 10 14 s −1 ) might be well suited for extensive production of these radioisotopes. Following the assessment discussed in [12,17] for 99 Mo/ 99m Tc, it is possible to make a first rough estimate of the specific activity for 64 Cu that can be produced at a 10 15 (taken as reference) 14 MeV neutron source, such as the New Sorgentina Fusion Source (NSFS), well described in [18,24]. This estimation can be made thanks to the results of the 64 Cu achieved in these experiments performed using the ENEA-FNG neutron beams and taking into account the simulation of the two reactions channels above benchmarked by experimental data measured and analysed at ENEA-INMRI.…”

Section: Perspectives For Higher Brilliance 14 Mev Neutron Sourcesmentioning

confidence: 99%

64Cu production by 14 MeV neutron beam

Capogni

Capone

Pietropaolo

et al. 2020

JNR

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64Cu is an emerging radionuclide of great interest in personalized nuclear medicine. It is produced by a cyclotron via the reaction 64Ni(p,n)64Cu. This production method increased during the last decades, because small biomedical cyclotrons can be easily installed close to the nuclear medicine department of a hospital. As a matter of fact, 64Ni is a very expensive target material. For this reason, an alternative 64Cu production method was investigated at ENEA by using the quasi-monochromatic 14 MeV fusion neutron beam made available at the Frascati Neutron Generator (FNG) located at the ENEA – Frascati Research Center. In particular, two nuclear reactions were studied: 65Cu(n,2n)64Cu and 64Zn(n,p)64Cu. The radiochemical analysis of the activated samples was performed at the ENEA-NMLNWM laboratory located in ENEA-Casaccia Research Center. The activity measurements were carried out at the ENEA-INMRI, located in the ENEA-Casaccia Research Center, with high metrological level conditions and by assuring their traceability to the 64Cu primary activity standard here developed and maintained. A prediction of the 64Cu production by means of the high-brilliance 14 MeV neutron source named Sorgentina is also discussed.

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“…An example is the ENEA project NSFS (New Sorgentina Fusion Source), an accelerator-driven 14 MeV neutron source whose main features are well described in refs. [2,3].…”

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confidence: 99%

“…Instead of approaching the case of NSFS, whose target design is presently under refinement, FNG is actually a D-T test facility and a reference laboratory to make predictions of the capabilities of a high-intensity D-T continuous neutron source, as NSFS will be. The quantitative assessment of the brilliance is made by modeling FNG as operating at a neutron emission rate of 10 15 s −1 , i.e., close to the one foreseen in NSFS [2,3]. Referring Fig.…”

mentioning

confidence: 99%

On the slowing-down of 14 MeV fusion neutrons: A spectrometry benchmark and perspectives on future neutron science facilities

Pietropaolo

Flammini

Moro

et al. 2019

EPL

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The spectral fluence rate of the thermalized neutron field obtained by slowing down the 14 MeV fusion neutrons produced at the accelerator-driven Frascati Neutron Generator is measured by means of the Bonner Sphere Spectrometer. Neutron thermalization is achieved by means of a moderator assembly made of a copper pre-moderator and a polyethylene moderator. A Monte Carlo simulation reproducing the experimental set-up is also performed by means of the MCNP code and the results are compared to the experimental data. The benchmarked Monte Carlo is then used to predict the brilliance of a thermal moderator operating at a potential highintensity 14 MeV neutron continuous source featuring a neutron emission rate of 10 15 s −1 . The results obtained show that if a D-T neutron source featuring a continuous neutron emission rate of 10 15 s −1 could be made operative, it could be effectively exploited for neutron science.

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Design optimization and performances of New Sorgentina Fusion Source (NSFS) supporting materials research

Cited by 8 publications

References 1 publication

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

64Cu production by 14 MeV neutron beam

On the slowing-down of 14 MeV fusion neutrons: A spectrometry benchmark and perspectives on future neutron science facilities

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