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1

Design of the neutron generator for the development of boron neutron capture therapy

Bezshyyko Oleg, Golinka-Bezshyyko Larysa

Bio-Algorithms and Med-Systems

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2023

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Vol. 19, no. 1

124--131

EN

In this article, we present the modern state of development of boron neutron capture therapy (BNCT) for cancer treatment using compact neutron generators. In the introduction we consider the main advantages and problems of the BNCT method, the main approaches and directions for building neutron sources, the development of chemical materials - boron-containing delivery agents and the control of irradiation of malignant tumours and healthy tissues. In the main part of the article we consider the main structures of neutron generators that can be effective for applying in BNCT. The development and building of a prototype of a compact neutron generator is also described.

2

Transcriptomic data analysis of melanocytes and melanoma cell lines of LAT transporter genes for precise medicine

Szczepanek Monika, Panek Dominik, Przybyło M., Moskal Paweł, Stępień Ewa Ł.

Bio-Algorithms and Med-Systems

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2022

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Vol. 18, no. 1

144--150

EN

Background: Boron Neutron Capture Therapy (BNCT) is a two-step treatment that can be used in some types of cancers. It involves administering a compound containing boron atoms to the patient and irradiating the affected area of the body with a neutron beam. The success of the therapy depends mainly on the delivery of the boron isotope (10B) to the tumor using an appropriate boron carrier. One of the boron carriers used is boronophenylalanine (BPA). Therefore, in research on the use of boron carriers, it is also important to know the mechanisms of its uptake by cells. Aim: To study the expression of LAT family genes in two melanoma (high melanotic WM115 and low melanotic WM266-4) cell lines and melanocytes (HEMa-Lp) which are responsible for the transport the BPA into cells. Methods: To normalize data from the transcriptomic analysis, the ratio of the median method was used. This allowed the samples to be compared with each other. Comparison metrics included log-fold change (LFC) values. The heatmap of LFC values and the cluster map were created. These graphs show the similarities and differences between the samples. Results: Transcriptomic data show that in melanocytes, LFC for SLC7A5 (LAT1) and SLC3A2 (4Fhc) was higher than in melanoma cell lines, which corresponded with their melanin content. Conclusion: Our results indicate overexpression of BPA transporter genes in normal cells (melanocytes), which may suggest the highest level of these proteins in melanocytes compared to less melanotic melanoma. Therefore, for BNCT, the use of BPA as the 10B carrier will require additional qualifying tests of amino acid transporter expression for patients and specific tumors to develop a personalized BNCT.

3

Reactor Laboratory for Biomedical Research in National Centre for Nuclear Research in Poland

Michaś Edyta, Dorosz Michał, Wójciuk Karolina, Tymińska Katarzyna, Wiliński Maciej, Maciak Maciej, Domański Szymon, Wojtania Grzegorz, Bartosik Łukasz, Małkiewicz Adam, Lechniak Jan, Gryziński Michał Aleksander

Polish Journal of Medical Physics and Engineering

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2021

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Vol. 27, Iss. 1

119--122

EN

National Centre for Nuclear Research, NCBJ is one of the biggest research institutes in Poland, in which scientists deal with basic research in the various fields of subatomic physics, development of nuclear technologies and practical applications of nuclear physics methods, including those for nuclear medicine and radiotherapy. NCBJ operates the only Polish nuclear research reactor MARIA, around which a Reactor Laboratory for Biomedical Research, RLBR has been built in the last 4 years. One of the main aims of the RLBR team is to adapt the H2 channel, one of the eight MARIA’s horizontal channels, to a specific irradiation facility delivering a high flux thermal/epithermal neutron beam. The beam derived from the channel will be a tool for biological, physical and material studies for Boron Neutron Capture Therapy, BNCT. While NCBJ is focused on building a neutron research facility, the Polish scientific community expressed its interest in BNCT development and implementation as an alternative therapy for cancer treatment. Through the working group meetings organized in the form of regular scientific workshops since 2015, it led to the establishment of a national scientific consortium dedicated to BNCT. Polish Consortium for Boron Neutron Capture Therapy agreement was initially signed by twelve institutions including scientific institutes, universities and oncological centres in October 2019. National Centre for Nuclear Research was appointed the leader of the consortium. A year later the consortium was enlarged by two more institutions.

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Badania nad terapią BNCT w Polsce i na świecie

Knake Natalia, Maciak Maciej, Maliszewska-Olejniczak Kamila, Tymińska Katarzyna, Murawski Łukasz, Madejowski Gaweł, Wójciuk Karolina, Michaś Edyta, Wojtania Grzegorz, Kuć Michał, Dróżdż Agnieszka, Gryziński Michał A.

Inżynier i Fizyk Medyczny

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2019

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Vol. 8, nr 4

289--295

PL

Przy Reaktorze MARIA w Narodowym Centrum Badań Jądrowych (NCBJ) powstaje stanowisko do badań nad terapią borowo-neutronową (BNCT). Terapia polega na napromienianiu nowotworu wiązką neutronów o odpowiednich parametrach po uprzednim podaniu pacjentowi związku boru, który w wyniku określonych mechanizmów gromadzi się głównie w komórkach rakowych. W wyniku reakcji 10B(n,α)7Li emitowane są cząstki jonizujące powodujące zniszczenie tylko tych komórek, w których zgromadzony jest bor [1]. Badania kliniczne prowadzone na świecie potwierdzają skuteczność metody, otwierając nowe perspektywy dla jej zastosowania w terapii konwencjonalnej.

EN

The stand for research on Boron Neutron Capture Therapy (BNCT) at the MARIA Reactor at the National Centre for Nuclear Research is being created. The therapy consists of irradiation of the tumour with a neutron beam with specific parameters after prior administration of the boron compound to the patient, which accumulates mainly in cancer cells as a result of specific mechanisms. As a result of 10B(n,α)7Li reaction, ionising particles are emitted and destroy only those cells, in which boron is accumulated. Clinical trials conducted in the world show relatively high efficiency of BNCT, opening new perspectives for its use in conventional therapy.

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Synteza proszków węglika boru z nieorganicznych źródeł węgla

Kozień D., Bućko M.M.

Materiały Ceramiczne

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2018

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T. 70, nr 4

301--312

PL

Węglik boru w postaci polikrystalicznych spieków jest tworzywem, którego właściwości stanowią o jego potencjalnym zastosowaniu zarówno jako materiału konstrukcyjnego, jak i funkcjonalnego. Ostatnio proszki węglika boru wzbudzają zainteresowanie jako źródło boru w terapii BNCT. Proszki węglika boru są zazwyczaj syntezowane poprzez karbotermiczną redukcję tlenowych związków boru: kwasu borowego lub tlenku boru. Reakcja tego typu prowadzi do silnego wzrostu krystalitów B4C i ich łączenia się w duże, mocne agregaty. Ideą prezentowanej pracy jest przeprowadzenie reakcji w niewielkich obszarach, zawierających obydwa prekursory, izolowanych od siebie nadmiarem jednej z faz. Do syntezy wykorzystano zawiesiny grafenu lub cząstek węgla aktywnego oraz roztwór żywicy fenolowo-formaldehydowej z boranem amonu. Wysuszone prekursory poddano obróbce cieplnej w 1500 °C, 1600 °C i 1700 °C przez 1 h w atmosferze argonu. Stwierdzono postęp reakcji syntezy B4C ze wzrostem temperatury, a także zmiany wielkości i pokroju jego ziaren. Widoczny jest również wpływ użytej fazy węglowej zarówno na skład fazowy, jak i morfologie proszków.

EN

Boron carbide in the form of polycrystalline sinters is a material whose properties determine its potential use both as a constructional material and as a functional material. Recently, boron carbide powders have aroused interest as a source of boron in BNCT therapy. Boron carbide powders are usually synthesized by carbothermic reduction of boron oxy compounds: boric acid or boron oxide. The reaction of this type leads to a strong growth of B4C crystallites and their joining into large, strong aggregates. The idea behind the presented work is to conduct reactions in small areas containing both precursors, isolated from each other by an excess of one of the phases. For the synthesis, suspensions of graphene or activated carbon particles and a solution of phenol-formaldehyde resin with ammonium borate were used. The dried precursors were heat treated at 1500 °C, 1600 °C and 1700 °C for 1 h under argon. The progress of the B4C synthesis reaction with the increase in temperature as well as the change in the size and size of its grains was found. The influence of the used carbon phase on both the phase composition and the morphology of the powders is also visible.

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CFD analysis of the safety related thermal hydraulic parameters describing a flow domain of an experimental medical installation (BNCT converter) inside of the Research Reactor MARIA

Prusiński P. A., Potempski S., Borysiewicz M., Kowal K., Kwiatkowski T., Prusiński A. M.

Journal of Power Technologies

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2012

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Vol. 92, nr 4

227--240

EN

The Boron-Neutron Capture Therapy (BNCT) is an experimental radiotherapy technique used to treat the most aggressive types of brain tumors that cannot be surgically removed from the human body. To date, clinical trials of BNCT have been initiated at only a handful of reactors around the world, but advanced studies on BNCT are still being carried out in numerous research centers where the suitable or convertible reactors are available. Construction of BNCT facilities is justified only at some existing reactors. Others can possibly be adapted for BNCT by using fission converters to modify the energy spectrum of the primary neutron beam, which makes it useful for treatment purposes. The BNCT converter, designed for use in the MARIA research reactor at the National Centre for Nuclear Research [W1] (NCBJ) in Świerk near Warsaw, Poland, consists of 99 fuel rods (containing low-enriched uranium) inside of the aluminum box. Since its installation affects the core layout and possibly may affect the normal operating regime of the reactor, additional safety analyses must be performed to prove the existence of sufficient safety margins. In this study modern Computational Fluid Dynamics (CFD) techniques have been applied to assess the maximum temperature of the rod wall surfaces, the temperature difference between the inlet and outlet of the converter channel, as well as the maximum and average velocity of the fluid and to compare them with the results presented in the reference analytical study.

7

Konstrukcja detektora rekombinacyjnego do dozymetrii promieniowania reaktorowego

Tulik R., Krzemiński Ł.

Elektronika : konstrukcje, technologie, zastosowania

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2011

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Vol. 52, nr 7

135-137

PL

Praca przedstawia konstrukcję detektora rekombinacyjnego o grafitowych elektrodach wypełnionego azotem, przeznaczonego do dozymetrii pól promieniowania mieszanego, przede wszystkim reaktorowego. Pomiary prądu ciemnego oraz charakterystyk prądowo - napięciowych skonstruowanego detektora potwierdziły prawidłowe działanie detektora. Dodatkowo skonstruowano moderator składający się z nakładek wykonanych z polietylenowych płyt. Moderator ma konstrukcję modułową, co umożliwia zmianę grubości materiału moderatora przed detektorem, na kierunku padania wiązki, oraz za detektorem, w granicach od 30 do 100 mm. Zastosowanie nakładek o różnej grubości pozwoli symulację pomiaru dawek na różnej głębokości w tkance, z uwzględnieniem spowalniania i rozpraszania neutronów epitermicznych. Skonstruowany detektor zostanie wykorzystany w pracach badawczych i pomiarach porównawczych jako model detektora przeznaczonego do pomiarów rutynowych.

EN

The paper presents a design of a nitrogen filled recombination detector with graphite electrodes, devoted for mixed radiation dosimetry, especially in nuclear reactor radiation fields. Measurements of dark current and saturation curves of the detector confirmed the correct performance of the detector. In addition, a moderator madę with polyethylene plates was prepared. Moderator is modular, therefore it is possible to change the thickness of the moderating materiał in the beam direction and behind the detector in the range from 30 mm to 100 mm. The use of cups of different thicknesses enables simulation of the absorbed dose measurement at different depths in tissue, with account for slowing down of neutrons and for epithermal neutrons scattering. The detector will be used for research and in intercomparison measurements as a model of the detector for routine measurements.

8

Studies of recombination chambers filled with nitrogen for BNCT dosimetry

Tulik P., Golnik N.

Nukleonika

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2009

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Vol. 54, No. 4

255-259

EN

Dosimetric characterization of therapy beams for boron neutron capture therapy (BNCT) involves determination of dose components and among them the “nitrogen” dose due to protons generated by neutron capture on 14N. In this work, investigations were carried out using a graphite recombination chamber in order to determine the 14N capture, gamma, and fast neutron dose components. The separation of the dose components is based on differences in the shape of the saturation curve, depending on the LET spectrum of the investigated radiation. The measurements were performed in reference radiation fields at the Institute of Atomic Energy at Świerk and at a reactor beam of the INP Řež (the Czech Republic). The gamma component was determined with an accuracy of about 5%, while the variations in its value could be monitored with an accuracy of about 0.5%. Relative changes in the beam components (thermal/fast neutrons) could be detected on line with an accuracy of about 5%. It was shown that the chamber with tissue-equivalent cups could be used for the determination of the 14N capture dose at different depths in tissue.

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Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers

Bilski P., Golnik N., Olko P., Pytel K., Tracz G., Tulik P., Zielczyński M.

Nukleonika

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2004

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Vol. 49, nr 2

51-56

EN

Boron neutron capture therapy (BNCT) is an experimental therapy of selected tumours, based on a nuclear reaction initiated by the capture of thermal neutron by the 10B nucleus. After 10B had been delivered selectively to tumour cells, it can be activated by neutrons to deliver locally lethal high-LET radiation. BNCT beams are complex mixed radiation fields, because of broad neutron energy range, presence of gamma contamination and necessity of precise determination of several dose components. The paper presents some results of the research project on BNCT dosimetry with activation foils, recombination chambers and TL detectors.

10

Numerical optimisation of the fission-converter and the filter/moderator arrangement for the Boron Neutron Capture Therapy

Tracz G., Dąbkowski L., Dworak D., Pytel K., Woźnicka U.

Nukleonika

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2003

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Vol. 48, nr 4

177-185

EN

The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for a BNCT (Boron Neutron Capture Therapy) facility to be located at the Polish research nuclear reactor MARIA at Świerk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised in order to moderate fission neutrons to epithermal energies and to get rid of both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both the high epithermal neutron flux and the suitably low level of beam contamination. The elimination of photons originated in the reactor core is an exceptional advantage of the proposed design. It brings one order of magnitude lower gamma radiation dose than the permissible dose in such a type of therapeutic facility is required. The MCNP and FLUKA codes have been used for the computations.