2nd Workshop on neutrons in medicine and homeland security

12 Sep 2019, 09:00 → 13 Sep 2019, 22:45 Europe/Warsaw

Thursday, 12 September

09:30 → 09:55 Coffee a priori

09:55 → 13:15 Boron Neutron Capture Therapy: Morning

09:55 Opening by prof. dr. hab. Mariusz Sadzikowski Vice-dean of the Faculty of Physics, Astronomy and Applied Computer Science of the Jagiellonian University in Kraków

10:05 Polish consortium for Boron Neutron Capture Therapy and the "Neutrony H2" project at the National Centre for Nuclear Research

Speaker: Michał Gryziński

BNCT2019_Gryzinski.pptx

10:30 Cancer treatments by neutrons

Speaker: Wolfgang Sauerwein (German Society for Boron Neutron Capture Therapy)

11:00 Novosibirsk Neutron Source for BNCT

At present, Boron Neutron Capture Therapy (BNCT) is considered to be a promising method for the treatment of tumors. The report presents the basics of BNCT, its development stages, the state of development of accelerator neutron sources for BNCT clinics and describes in detail the Novosibirsk accelerator neutron source. This source is a state-of-the-art device comprised of i) the Vacuum Insulation Tandem Accelerator (VITA) - a new type of charged particle accelerator, ii) an advanced solid lithium target with superior resistance to blistering, and iii) a neutron Beam Shaping Assembly. At VITA characterized by a high acceleration rate of charged particles a stationary proton beam with an energy of 2.3 MeV and a current of 9 mA, sufficient for therapy, was obtained. A neutron-producing target optimal for forming an epithermal neutron flux that meets the requirements of BNCT has been developed and experimentally studied. To confirm the required quality of the neutron beam, the effect of neutron radiation on cell cultures and laboratory animals was studied. In the near future, it is planned to prepare a “handmade” Novosibirsk source for conducting therapy and to implement BNCT in 2022. The Novosibirsk source became the prototype source being built for the clinic in Xiamen (China) - one of the first five BNCT clinics. In addition to being used in BNCT, the source was used to determine dangerous impurities in ceramics for ITER and is planned to be used for radiation testing of the optical fiber and photomultiplier for CERN. In the latter case, the hydrogen beam will be replaced by a deuterium one. The report gives the construction of the source, presents the results of the research and declares the plans.

Speaker: Sergey Taskaev

11:30 Discussion session over coffee

12:00 Accelerator based BNCT in Poland?

Polish R&D program for Boron Neutron Capture Therapy (BNCT) started in 2001 and is presently coordinated by the National Centre for Nuclear Research (NCBJ) at Świerk/Otwock. The program aims to put in operation the dedicated research BNCT beam line at Maria reactor at Świerk and to offer this beam for R&D related to BNCT. At present, the interest of physicians in the project is limited since no clinical activities are planned.
There is an increasing interest worldwide in BNCT due to progress in construction of cheap and efficient accelerator-based sources of epithermal neutrons. The aim of this paper is to demonstrate that there is a sufficient technological and medical competence to build in Poland within 5-8 years a hospital based accelerator facility for BNCT. Relatively small installation can be located in an existing oncological clinic e.g. in central Poland. In parallel, the neutron beam at NCBJ can be very useful for research, training, calibration etc. Broadening the scope of the Polish BNCT project towards the clinical application can give some more impetus for our activities.

Speaker: Paweł Olko (IFJ PNA)

BNCT2019_Olko.ppt

12:25 Boron Loaded Nucleic Acids and Their Assembly Into Functional Nanoparticles

Damian Kaniowski,a Katarzyna Ebenryter-Olbińska,a Katarzyna Kulik,a Slawomir Janczak,b Anna Maciaszek,a Katarzyna Bednarska-Szczepaniak,b Barbara Nawrota and Zbigniew J. Leśnikowskib

aCentre of Molecular and Macromolecular Studies, Polish Academy of Sciences, Sienkiewicza 112, 90-363 Lodz, Poland; bInstitute of Medical Biology, Polish Academy of Sciences, Lodowa 106 92-232, Lodz, Poland

Nucleic acids, while retaining their status as “the molecules of life,” are becoming “molecular wires,” i.e., materials for the construction of molecular structures at the junction between the biological and inorganic worlds [1]. Natural as well as modified nucleic acids are used in practice. Unmodified nucleic acids are easily accessible because of the availability of automated chemical methods for nucleic acids synthesis, but their properties are ordinary. The aim of the second approach is the incorporation of new, “unnatural” properties, which is usually performed by adding suitable labels and modifying units into nucleic acids.
One of the original openings in nucleic acids modification were derivatives containing of boron cluster (polyhedral boron hydrides) component [2]. Herein, we will discuss the use of boron clusters as a platform in the design of a new type of bioinorganic composites comprising nucleic acids and boron clusters and will discuss some of their properties and applications [3-7].

References: [1] Lesnikowski, Z.J., Cur. Org. Chem., 2007, 11, 355; [2] Lesnikowski, Z.J., Eur. J. Org. Chem., 2003, 4489; [3] Ebenryter-Olbińska, K., et al., Chem. Eur. J., 2017, 23, 16535; [4] Kaniowski, D., et al., Molecules, 2017, 22, 1393; [5] Olejniczak, A.B., et al., Int. J. Mol. Sc., 2018, 19, 3501; [6] Leśnikowski, Z.J., J. Med. Chem. 2016, 59, 7738; [7] Adamska-Bartłomiejczyk, A., et al., in “Boron-Based Compounds: Potential and Emerging Applications in Medicine”, (E-M. Hey-Hawkins, C. Vinas-Teixidor, Eds.,), John Wiley & Sons, Inc., Chapter 1.2, pp 20-34, 2018.

Acknowledgments: This work was supported in part by the National Science Center, Poland, grant 015/16/W/ST5/00413. Contributions from the Statutory Fund of IMB PAS (S.J, Z.J.L., K.B-S) and CMMS PAS (B.N., K.E-O., K.K., D.K., A.M.) are also gratefully acknowledged.

Speaker: Zbigniew J. Leśnikowski (Institute of Medical Biology, Polish Academy of Sciences)

BNCT2019_Lesnikowski.ppt

12:50 J-PET technology - steps towards theranostics

Speaker: Ewa Stępień (Jagiellonian University)

13:15 → 14:45 Lunch & coffee

14:45 → 15:55 Boron Neutron Capture Therapy: Afternoon

14:45 Vascular network investigation by X-ray microtomography

Carcinogenesis is a process providing cell DNA changes. As a consequence, cells begin to divide rapidly. The cancerous tissue growth requires an increased supply of nutrients and oxygen therefore the tumor needs to produce its own irregular blood vessels network. Combating pathological angiogenesis is one of the basic strategies of anticancer therapy.
There are a few methods capable of visualizing and analyzing vascular network. Some of the methods, such as histology, are destructive, others, like magnetic resonance imaging (MRI), does not produce images with sufficient resolution. X-ray microtomography (microCT) is a well-established nondestructive method for 3D imaging and analysis of small samples. As a result, micro-CT obtains spatial distribution of X-ray linear attenuation coefficient within the sample.
Unfortunately, the difference in linear attenuation coefficient between blood in the vessels and surrounding soft tissues is nondetectable with „raw micro-CT". There are several ways to improve vessels visibility in micro-CT image, for example staining or perfusion.
This presentation will provide an overview of vessels visualization and analysis methods with examples, performed in Micro-CT Lab of Medical Physics department at Jagiellonian University [1,2].

References
[1] Leszczyński, B., Sojka-Leszczyńska, P., Wojtysiak, D., Wróbel, A. and Pędrys, R. (2018). Visualization of porcine eye anatomy by X-ray microtomography. Experimental Eye Research, 167, pp.51-55.
[2] Leszczyński, B., Śniegocka, M., Wróbel, A., Pędrys, R., Szczygieł, M., Romanowska-Dixon, B., Urbańska, K. and Elas, M. (2018). Visualization and Quantitative 3D Analysis of Intraocular Melanoma and Its Vascularization in a Hamster Eye. International Journal of Molecular Sciences, 19(2), p.332.

Speaker: Bartosz Leszczyński (M. Smoluchowski Institute of Physics, Jagiellonian University, Kraków, Poland )

BNCT2019_Leszczynski.pptx

15:05 GEANT4 study of a BNCT applicable neutron beam achievement from compact DD, DT neutron generators

An evaluation of the design of BSA for BNCT is discussed based on GEANT4 simulations. To create the realistic model by GEANT4 program there are inserted two physics lists for nuclear and electromagnetic reactions. The feasibility study describes the thermalization of neutrons from two different neutron sources based on DD, DT compact neutron generators.
In some cases, a multiplier, based on (n,2n) nuclear reactions, is used to increase the flux of thermal/epithermal neutrons. The selection of effective materials as moderators and reflectors playing the main role to get a proper neutron flux. Due to different types of neutron sources, BSA designs cannot be the same, but some materials are usable for all of them.
The comparison between different types of BSA used to find optimal materials, but the key role plays a neutron source to provide a usable neutron flux, which will be consistent with IAEA recommendations.

Speaker: Vahagn Ivanyan (Jagiellonian University)

BNCT2019_Ivanyan.ppt

15:30 Potential application of Y2O3 and CaF2 ceramic in medicine

Speaker: Andrzej Kruk (Pedagogical University of Cracow)

16:00 → 19:20 Polish Consortium for boron neutron therapy internal meeting

Friday, 13 September

09:30 → 10:00 Coffee a priori

10:00 → 13:00 Neutrons in Homeland Security: Morning

10:00 Dumped Munitions in the Baltic

Chemical and conventional ammunition dumped in the Baltic Sea and the Skagerrak contain a wide range of hazardous substances. Considering the growing use of the seabed for economic purposes (offshore wind farms, pipelines etc.), the likelihood of disturbing dumped containers with chemical warfare agents, causing direct emissions to the surrounding environment and risk of human and wildlife exposure, is increasing. In addition, the containers are deteriorating due to e.g. corrosion. For all these reasons there is an ongoing discussion on how to assess and manage the environmental risk of dumped ammunition, especially in areas where their location is likely to cause a conflict with maritime activities.
DAIMON aims to increase the knowledge base on how to evaluate the risks and benefits of various management options.
DAIMON has performed several studies in both conventional and chemical munition dumpsites. This studies included different risk factors, such as density of munitions on seabed, their corrosion status and pollution of nearby sediments. New approaches for analysis of both CWAs and toxic explosive related chemicals on a one method using sophisticated high resolution mass spectrometry have been tested and applied in pilot studies, Further experiments were carried out to confirm the structure of newly discovered CWAs using liquid chromatography, NMR and LC–MS. Two analyte structures were confirmed. Further work to identify the remaining three novel chemicals is underway. One of these may be significant due to relatively high concentrations in some studied sediment samples.
Also currents and leakage rate were estimated, and probability of pollution modelled. This data sets were complimented by studies of biota – biomarkers of environmental stress, bioacumullation of toxic agents and their toxicity. Preliminary chemical data indicate exposure of fish in the dumpsite to chemical warfare agents. Studies in a dumpsite of conventional munitions in Kiel Bight reveal an elevated prevalence of neoplastic lesions (liver tumours and pre-stages) in flatfish (dab, Limanda limanda) from the area
In DAIMON a special neural net structure is used to constituate the decision support module based on abovementioned data. It forms a categorisation algorithm which enables one hand side an on-line categorisation of selected places, regions or special enviromental situations, otherwise elaborate a short and log time prognosis. This enables an adaptive system for different players like administrations, offices or users can be supported by client specific situation reports.

Speaker: Jacek Bełdowski (Instytut Oceanologii PAN)

BNCT2019_Beldowski.pptx

10:25 Application of the anti-Compton shielding in the gamma spectrometer of the SWAN neutron explosives detector

Application of Neutron Activation Analysis for revealing isotopic composition of the content of sealed containers catches attention of any security officer. It is a matter of fact though, that neutron radiation is not easy to handle, and any device employing it in its operating principle is bound to include tricky solutions to a number of challenges. One of them is enormous background which can overload any acquisition system. We present the detection setup of the SWAN neutron explosives detector, designed to suppress the background of incoming gamma radiation.

Speaker: Michał Gierlik (NCBJ)

BNCT2019_Gierlik.pdf

10:50 Underwater detection of hazardous substances with neutrons: the SABAT project

Speaker: Michał Silarski (Jagiellonian University)

BNCT2019_Silarski.pptx

11:10 Discussion session over coffee

11:40 MCNP simulations for chemical threat detection with neutrons and POLFEL Free Electron Laser beam dump modelling

A Monte Carlo N-Particle transport code (MCNP) is exceptionally useful tool for many nuclear systems designing and its optimization. The code is widely used in many task concerning nuclear reactors operation, homeland security, threat detection using neutron sources, radiation safety and many others. Basically, the MCNP work principle is based on transportation of particles through virtually designed medium with respect to reaction cross sections implemented in the program. Finally, the desired simulation output can be set, in example, as an average flux through volume or pulse height distribution. In this presentation, the MCNP simulations for threat detection using neutron activation and POLFEL free electron laser beam dump performance will be presented.

Speaker: Paweł Sibczyński (National Centre for Nuclear Research)

BNCT2019_Sibczynski.pdf

12:05 Apparatus neutron sources at IFJ PAN for basic and application research

Two types of apparatus neutron sources are present at IFJ PAN: neutron generator (IGN-14) and two plasma focus devices (PF-4 and PF-24). IGN-14 is a pulsed deuteron accelerator which generates 14 MeV or 2.45 MeV neutrons, when a tritium T/Ti or deuterium D/Au target is used, respectively. The plasma focus is a device that produces, by electromagnetic acceleration and compression, short-lived, hot and dense plasma in a gas. This plasma emits fast neutrons produced by nuclear fusion reaction when a deuterium or deuterium mixture is a working gas. These sources are used for basic and application research. The fundamental studies cover (among others) the research of plasma and nuclear fusion, the determination of plasma parameters and imaging, as well as computer modeling of the nuclear radiation. The applications include the testing of the detectors. As an example: the studies of the neutron emission from discharges in deuterium, in PF-24, and elaboration of a method for detection of explosives and other illicit materials by a single nanosecond neutron pulses with using Monte Carlo methods, will be presented.

Speaker: Agnieszka Kulińska (IFJ PAN)

BNCT2019_Kulinska.pptx

12:35 Techniques for data processing in real-time using FPGAs

The presentation will cover modern techniques for developing data acquisition systems capable for high-level processing of data in real-time regime.

Speaker: Grzegorz Korcyl (Jagiellonian University)

BNCT2019_Korcyl.pptx

13:00 → 14:30 Lunch & coffee

14:30 → 15:45 Neutrons in Homeland Security: Afternoon

14:30 Geant4 simulation of optical photon transport in monolithic crystal scintillator with readout by silicon photomultiplier array.

GEANT4-based Monte Carlo simulation has been performed for a cylindrical shape single-crystal scintillators in order to evaluate the possibility of using position sensitive response of the silicon photomultiplier (SiPM) array to perform gamma sources localization with the target on pulsed fast neutron analysis (PFNA). PFNA utilized microsecond wide fast neutron pulses produced by electronic neutron generator to initiate fast neutron inelastic scattering reactions on nuclei. Characteristic combination of prompt -rays from nitrogen, carbon and oxygen nuclei excitations is an evidence of presence explosive materials. Since the fluorescence decay time of widely used and relatively cheap NaI, BGO and CsI scintillators can reach 300-1000 ns, pulse pile-ups become serious problem that cause resolution degradation, spectral distortion and peak position shift. In this case the choice is to use fast LaBr3(Ce) scintillator with <30 ns decay time. But this scintillator is 10-20 times more expensive and has relatively high intrinsic radiation background. To address these issues cylindrical shape monolithic scintillators directly coupled SiPMs arrays for double side readout were simulated using Geant4 optical transport. According to preliminary simulation results high energy gamma rays in the range 4-7 MeV undergo multiple Compton scattering inside the simulated 2"×2" cylindrical crystal several percent of such events form the scattering and absorption clusters spatially separated. Calculating center of gravity of this clusters allow to apply Compton imaging method to localize gamma source. Additionally, cluster analysis allow to separate gamma scattering events from alpha particle absorption events which are the main source of intrinsic background of LaBr3(Ce) scintillator thus improving its detection sensitivity. Besides, in case of two gamma quanta hitting the crystal simultaneously cluster analysis can recognize such events and reject pile-up pulses. This will allow to use relatively slow NaI(Tl) and BGO scintillators for imaging gamma sources for the PFNA application.

Speaker: Anzori Georgadze (Kiev Institute for Nuclear Research)

BNCT2019_Georgadze.ppt

14:55 Advanced Hydrated Cement Composite Materials for Gamma and Neutron Shielding Applications

Dominika Madej

AGH University of Science and Technology
Faculty of Materials Science and Ceramics
al. A. Mickiewicza 30
30-059 Krakow, Poland
*dmadej@agh.edu.pl

Many different types of hydrated cement composite materials and concretes, which contain light and heavy elements, have been used in building construction and radiation shielding for years.
One of the main points about popularity of hydrated cements and concretes is its hydrogen content for neutron shielding. Cements containing barium and especially strontium may be considered for shielding against gamma or X-ray radiation.
This work summarizes the hydration behaviour of state-of-the-art cements belonging to the CaO-Al2O3-ZrO2 system doped with metal cations with different valence states. The effects of Sr-, Ba- or Fe-doping of the Ca7ZrAl6O18 were investigated with the objectives to assess the effects of structure modifications on hydraulic behaviour of this phase. Strategies for the incorporation of Sr, Ba or Fe into the structure of calcium aluminates are necessary for the potential application of these hydraulic binder materials as ingredients of high temperature resistant heavy concretes.
The hydration products formed in the Sr, Ba or Fe-doped CaO-Al2O3-ZrO2-H2O and SrO-Al2O3-H2O cement pastes were subjected to morphological, chemical and structural characterization using X-ray diffraction (XRD), Fourier Transform Infrared Spectroscopy (FTIR) and Scanning Electron Microscopy with Energy Dispersive Spectroscopy (SEM-EDS) techniques. The thermal stability and dehydration mechanism of hydrates were assessed by simultaneous thermal analysis i.e. Thermogravimetry (TG) and Differential Scanning Calorimetry (DSC) at different hydration times. The detailed thermal decomposition mechanism of the hydrated cement materials has been clarified based on Evolved-Gas-Analysis data with a Quadrupole Mass Spectrometer (QMS).

Acknowledgements
This project is financed by the National Science Centre, Poland, Project Number 2017/26/D/ST8/00012 (Recipient: Dominika Madej).

Speaker: Dominika Madej (AGH University of Science and Technology, Faculty of Materials Science and Ceramics)

BNCT2019_Madej.ppt

15:20 Review of plastic scintillators for neutron detection

Speaker: Łukasz Kapłon (Jagiellonian University)

BNCT2019_Kaplon.pdf

16:00 → 17:15 Tutorial on radiation dose calculation with the MCNP package

Speaker: Pawel Sibczynski (National Centre for Nuclear Research)

17:30 → 21:30 Conference dinner