Neutron dose estimation in a zero power nuclear reactor

Triviño, Sebastián; Vedelago, José; Cantargi, F.; Keil, Walter Miguel; Figueroa, R.; Mattea, Facundo; Chautemps, A.; Santibáñez, M.; Valente, M.

doi:10.1016/j.radphyschem.2016.06.011

Cited by 4 publications

(5 citation statements)

References 30 publications

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“…The RA-0 Nuclear Reactor, a zero power reactor that belongs to the National Atomic Energy Commission (CNEA) and it is currently placed at the Universidad Nacional de Córdoba (UNC), Argentina, was used as a neutron source 40 . The reactor normally operates at a power of 1 W. The fuel elements are vertically located in an aluminum ring structure and are composed of a mixture of UO enriched 20 % in U, graphite and pitch located inside an aluminum sheath with an active length of 54 cm, while light water is used as a neutron moderator.…”

Section: Methodsmentioning

confidence: 99%

“…The samples were placed in the central irradiation channel of the reactor core. The dose absorbed by each dosimeter was calculated by means of the Monte Carlo transport code MCNP according to the procedure described elsewhere 40 . In the simulations, the contributions from photons, neutron elastic scattering and neutron absorption were discriminated so that the capture events could be quantified.…”

Section: Methodsmentioning

confidence: 99%

“…In medical physics, gel dosimeters doped with compounds based on B are used to mimic BNCT treatments and thus quantifying the neutron capture dose contribution 38 . Although many of these detection systems are capable of determining the neutron contribution, most of them still require signal post-processing and calculations in order to discriminate the neutron contribution to the total absorbed dose 39 , 40 .…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Smart material based on boron crosslinked polymers with potential applications in cancer radiation therapy

Vedelago

Mattea

Triviño³

et al. 2021

Sci Rep

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Organoboron compounds have been playing an increasingly important role in analytical chemistry, material science, health applications, and particularly as functional polymers like boron carriers for cancer therapy. There are two main applications of boron isotopes in radiation cancer therapy, Boron Neutron Capture Therapy and Proton Boron Fusion Therapy. In this study, a novel and original material consisting of a three-dimensional polymer network crosslinked with $$^{10}$$ 10 B enriched boric acid molecules is proposed and synthesized. The effects of the exposition to thermal neutrons were studied analyzing changes in the mechanical properties of the proposed material. Dedicated Monte Carlo simulations, based on MCNP and FLUKA main codes, were performed to characterize interactions of the proposed material with neutrons, photons, and charged particles typically present in mixed fields in nuclear reactor irradiations. Experimental results and Monte Carlo simulations were in agreement, thus justifying further studies of this promising material.

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Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Smart material based on boron crosslinked polymers with potential applications in cancer radiation therapy

Vedelago

Mattea

Triviño³

et al. 2021

Sci Rep

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“…Fricke gel dosimeters were manufactured according to the method described elsewhere [23,24]. Their xylenol orange concentration was set to ppm to reduce any interference with the Ag NPs plasmonic signal.…”

Section: Fricke Gel Dosimetrymentioning

confidence: 99%

Green synthesis of silver nanoparticles aimed at improving theranostics

Vedelago

Gómez

Valente

et al. 2018

Radiation Physics and Chemistry

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“…Surgery is usually used for initial treatment when the condition of the tumor is still in its early stages [7]. Such cancer treatment can cause side effects that occur when treatment affects tissues or healthy organs[1] [18] [19][20]. .To overcome these weaknesses BNCT has been developed with selective characteristic to cancer cells.…”

Section: Introduction mentioning

confidence: 99%

Neutron Characterization of BNCT Water Phantom Based on Kartini Research Reactor Using PHITS

Hutaria

Susilo

Sardjono

2019

ijpna

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Boron Neutron Capture Therapy (BNCT) is a therapy that utilizes the interaction of thermal neutrons with a boron-10 core that produces alpha particles and lithium nuclei. The result of this boron reaction has high linear energy transfer (LET). BNCT has an advantage over other radiation therapy in that it has a high selectivity level. This research was run using PHITS simulation to find out the value of neutron flux spread over a water phantom. The conclusion of the research is the distribution of neutron flux in the water phantom without boron is higher the the distribution of neutron flux in the water phantom containing boron

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Neutron dose estimation in a zero power nuclear reactor

Cited by 4 publications

References 30 publications

Smart material based on boron crosslinked polymers with potential applications in cancer radiation therapy

Smart material based on boron crosslinked polymers with potential applications in cancer radiation therapy

Green synthesis of silver nanoparticles aimed at improving theranostics

Neutron Characterization of BNCT Water Phantom Based on Kartini Research Reactor Using PHITS

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