Nuclear Research Center Research Articles

Determination of Activity Concentrations and Internal Dose Assessments in Urine from Workers in Iraqi Nuclear Research Center, Iraq

To detect tritium levels in the human body, tritium in the urine must be measured. The investigation of the level of tritium activity in the urine of workers of the Iraqi Nuclear Research Center (INRC) has been realized in order to assess vocational exposure levels. Three worker groups in INRCs were chosen, involved in the Central Laboratories Directorate (CLD), the Decommissioning Directorate (DD), and the Radioactive Waste Treatment and Radioactive Waste Store Directorate (WTWSD), among others in Al-Tuwiatha site, in addition to the control group, as the research targets. Tritium concentration was determined in urine samples from 52 workers (aged 32-61) and 13 control people (aged 30-58). 65 urine samples of 50 mL were collected and analyzed. The Eichrom's Tritium Column way was used to handle the samples of urine, and the distillate tritium activity concentration was then assessed using Liquid Scintillation Counter. The effective and annual effective doses were estimated for the internal doses. The accuracy of urine sample measurements had been tested. The highest level of tritium activity samples of urine from three groups of workers in INRCs is 65.401 Bq/L, and for control group is 39.300 Bq/L, activity of tritium concentrations estimated by using counting scintillation of liquid (LSC) were found to be lower than Minimum Detectable Activity (MDA) of 1.95 Bq/L. The effective and annual effective dose from tritium was also assessed depend on results measured previously and standard values adapted by the International Commission on Radiological Protection. The effective highest doses for workers groups and control group were 497.048 ×10-3 and 298.680×10-3 nSv respectively. Highest annual effective dose 5757.773×10-3 and 5167.042×10-3 nSv respectively. These results were lowest than the allowed effective dose for the workers.

Investigation of the Effects of Ion Sources and RF Power on the Neutron Production Rate at SNRTC-IEC Fusion Device

Studies on an inertial electrostatic confinement (IEC) device are generally focused on increasing particle production. One way to achieve this is to increase the number of ion sources. In this study, the deuterium-deuterium fusion reaction was carried out in the IEC Saraykoy Nuclear Research and Training Center (SNRTC-IEC) fusion device (previously at the Turkish Atomic Energy Authority, now reestablished as the Turkish Energy, Nuclear and Mineral Research Agency) at cathode voltage of 85 kV and pressure of 5 × 10−4 mbars, and the effect of ion sources and radio-frequency (RF) power on the neutron production rate was investigated. To ensure a high concentration of ions in the center of the cathode, three inductively coupled plasma deuterium ion sources were added to this device. As the number of ion sources increased from one to three, the neutron production rate increased from 2.3 × 104 to 3.6 × 105n/s. Two ion source configurations were used to examine the effect of RF power. It was observed that when the RF power was increased from 40 to 200 W, the neutron production rate increased linearly from 4.6 × 104 to 1.7 × 105 n/s.

A novel irradiation module for ANICCA fuel cycle code based on multi-task learning

This paper introduces an alternative approach to irradiation modelling within the context of nuclear fuel cycle codes like ANICCA, the fuel cycle code developed by the Belgian Nuclear Research Centre (SCK CEN). The focus lies on upgrading the irradiation module by substituting the CRAM-based depletion calculations for a more flexible and innovative approach based on Multi-Task Learning (MTL). Utilizing data generated with SERPENT2 Monte Carlo simulations, two MTL neural networks are developed to surrogate irradiation processes of Uranium Oxide (UOX) and Mixed Oxide (MOX) fuels, respectively. MTL enables simultaneous learning of the evolution of the inventories for different observables – i.e., transuranium elements, fission products, minor actinides and fertile materials – offering improved predictive capabilities compared to non-MTL neural networks, as demonstrated in the cross-validation tests.Hyperparameters of the models were found using Bayesian optimization, resulting in superior model performance compared to the old CRAM-based model. Verification against SERPENT2, used as a reference code for comparison, demonstrates the stability and accuracy of the MTL-based models, outperforming the original CRAM method for the majority of predicted isotopes.

Design of SWRO Desalination Plant for Nuclear Research Center

Libya has an infinite water resource available inthe coastal towns and cities being located on Mediterranean Sea with 1950km coast. Therefore, the need for desalinatedwater for Nuclear Research Center NRC located in Tajurais currently about 1200 m3/day. To cover the center presentand future water needs for research and developmentactivities, two thermal sea water desalination plants have been assembled in the site. One of the plants uses MultiStage Flash technology and the other one uses Multi EffectDesalination technology with capacity of 1200m/day eachone. Detailed design for 1200m3/day seawater reverseosmosis SWRO unit is carried out using ROSA S oftware to make the technical comparison with other MSF and MEDunits. The unit labeled an S W30XLE-440i by the results ofthe Software is selected since it required the lower feedpressure of 55.5bar and highest salt recovery of 45% with total dissolved solid of 190ppm. From the technical point ofview, the study showed that SWRO required lower seawater inlet flow rate than MSF and MED. The unitsefficiency are 43%, 10.5% and 25% for SWRO, MSF, andMED, respectively. Further the Product quality TDS 190ppm for RO unit is suitable for drinking water, whilethose of MSF and MED 50ppm. Energy consumption asheating steam is not required for the S WRO unit; however,a steam flow rate 7.3m 3/hr is required by MSF and MEDunits. These make SWRO unit friendlier to the environment and most proper technically under these situations.

Evaluating Radiation Exposure to Oral Tissues in C-Arm Fluoroscopy A Dose Analysis

This study investigates the radiation dose to oral mucosal tissues during C-arm fluoroscopy imaging using an Alderson Rando phantom and thermoluminescent dosimeters (TLD-100) for precise measurements. The aim is to assess the potential risks for patients and healthcare personnel exposed to ionising radiation during these procedures. The Alderson Rando phantom, a human-equivalent model, was utilized to simulate radiation exposure in a controlled environment. TLD-100 dosimeters were strategically positioned in the 6th section of the phantom and exposed to radiation at intervals of 0.5, 1, 2, 4, and 8 minutes. The experiments were carried out at Hisar Hospital Intercontinental and the dosimeter readings were then evaluated at Çekmece Nuclear Research Centre. The study demonstrated that the mean radiation doses affecting the internal tissue of the oral mucosa were 0.912 mSv (0.5 minutes), 1.604 mSv (1 minute), 2.719 mSv (2 minutes), 6.763 mSv (4 minutes), and 13.811 mSv (8 minutes). The mean radiation doses affecting the lip skin tissue were 1.423 mSv (0.5 minutes), 2.435 mSv (1 minute), 5.2 mSv (2 minutes), 10.195 mSv (4 minutes), and 17.404 mSv (8 minutes). Results indicate a direct relationship between radiation dose and exposure time, with increasing doses observed at longer exposure times. This research aims to improve patient safety during C-arm scope imaging procedures by determining precise radiation dosage levels for oral mucosal tissues and addressing the lack of published reference values in the literature.

Development and validation of a Bayesian unfolding program using OpenBUGS open-source software for Bonner spheres neutron spectrometry

This study presents the development of a novel unfolding program based on a Bayesian method for Bonner spheres spectrometry. The program incorporates a priori information on the neutron spectrum, employing a linear superposition of three non-negative parametric functions: thermal-Maxwellian distribution, an intermediate region represented by a straight line in lethargy space (1/E behavior), and the Watt fission distribution for the fast region. The effectiveness of the developed program was validated through its application to two reference cases from the EURADOS 2018 exercise (LINAC and Skyshine), followed by its implementation in characterizing the neutron field around an OB26 neutron irradiator at the Secondary Standards Dosimetry Laboratory (SSDL) of the Nuclear Research Center of Algiers (CRNA), Algeria. While validation results for the LINAC case were promising, achieving comparable neutron spectrum shape and integral quantities to the reference, challenges were encountered with the Skyshine case. However, these challenges were partially addressed through sensitivity analysis, resulting in slightly improved outcomes compared to the previous participation and to the reference. Application of the program to characterize the neutron field around the OB26 irradiator yielded satisfactory results when compared to reference data. A two-step sensitivity analysis further enhanced the outcomes, initially substituting the Watt fission distribution with the evaporation distribution, thereby improving spectrum shape and integral quantities. Subsequently, utilizing the obtained neutron spectra as prior information for unfolding codes MAXED and GRAVEL ensured stability and agreement with reference data and preliminary results.

Cryogenic Distribution System for Polish Free Electron Laser Facility

Polish Free Electron Laser facility (PolFEL), presently under construction at the National Centre for Nuclear Research in Warsaw, will consist of an electron gun and four cryomodules each housing two 9-cell superconducting TESLA RF cavities. The cryomodules comprising the cavities will be supplied with superfluid helium at 2 K. Other PolFEL cooling power requirements result from the demand of the power couplers for the accelerating cryomodules (5 K) and thermal shields (40 K – 80 K). The machine will make use of several helium thermodynamic states like two-phase superfluid HeII, supercritical helium and low-pressure helium vapours supplied to cold compressors. A Cryogenic Distribution System (CDS) will provide supercritical helium to the valve-boxes where thermodynamic processing of the helium to a superfluid state will take place. The paper presents the CDS architecture and discusses the possible design options like methods of the power couplers cooling, optional use and location of cold compressors. The second law of thermodynamics has been used for the optimization of the CDS configuration. A generalized approach to the design of helium distribution systems, taking into account thermomechanical aspects and the consequences of the second law of thermodynamics, is presented.

Performance assessment and further optimization of the activation based criticality dosimetry system at the Belgian nuclear research centre SCK CEN

In places where fissile materials are being handled, the risk of a criticality accident can never be absolutely eliminated. Criticality accidents require specialized dosimetry techniques, which differ markedly from those used in routine radiological protection. This is caused by the fact that one should be able to measure very high doses up to 10 Gy in mixed gamma and neutron fields with very high instantaneous dose rates up to 105 Gy/s and complex energy spectra. The criticality dosimetry system at the Belgian Nuclear Research Centre SCK CEN is accredited according to ISO 17025 by the Belgian accreditation body BELAC and is used to monitor about 4000 nuclear workers. The system is based on a dedicated criticality dosemeter with four activation detectors (gold foils with and without cadmium shielding, an indium foil and sulphur pellets) and an iterative unfolding algorithm starting from a guess neutron fluence energy spectrum. This work describes the design of the SCK CEN criticality dosemeters and the iterative unfolding algorithm. Furthermore, it also discusses two new developments. Firstly, effective neutron reaction cross sections were calculated by MCNP6.2 Monte Carlo radiation transport simulations to be used in the unfolding algorithm. These effective cross sections take into account the effects of the dosemeter, the potential presence of the body and the neutron angle of incidence. These effects were demonstrated to be important, especially for the gold foils and if the dosemeter is worn against the body. Secondly, a Bayesian unfolding algorithm based on a parametric description of the neutron fluence energy spectrum was developed and tested. The results of this new algorithm were in good agreement with the iterative algorithm. The uncertainty assessment was more realistic with the Bayesian algorithm because it includes also the uncertainty associated with the unfolding process. However, for spectra that cannot be well described by the parametric function, the Bayesian algorithm can lead to significant under- or overestimations. In case sufficient information is available, it is better to make use of the iterative algorithm with a realistic guess spectrum to start from. Finally, this work also demonstrated the compliance of the SCK CEN criticality dosimetry system with the IAEA criteria for criticality dosimetry systems.

On Multi-Component Gas Migration in Single-Phase Systems

The present work deals with diffusion of gases in fully saturated porous media. We test and validate the gas transport mechanism of dissolution and diffusion, implemented in the TH2M process class in the open-source finite-element software OpenGeoSys. We discuss the importance of gas diffusion for the integrity of the multi-barrier system. Furthermore, we present a multi-component mass balance equation implementation in Python, which serves as a reference for the two-component TH2M implementation and allows for a discussion of multi-component gas diffusion in liquids. We verify and validate the numerical implementations as follows: First, we come up with a set of numerical benchmarks in which solutions obtained by the two-component TH2M and multi-component implementations are compared. Thus, we show under which conditions predictions made by the TH2M model can be used for multi-component gas systems. Finally, the work is validated using a through diffusion experiment performed at Belgium’s Nuclear Research Centre SCK CEN and a sensitivity analysis is conducted based on the featured experiment. The results of this work illustrate that predictions by both the two- and four-component models match the laboratory findings very well. Therefore, we conclude that also the two-component implementation can reflect the multi-component processes well under the given constraints such as full saturation.

A new technique for using gamma irradiation to enhance silver nanoparticles synthesized by chemical reduction and their effect on tomato early blight disease under field conditions

Early blight disease causes a significant loss in tomato production. This study focuses on the effective suppression of Alternaria solani, which causes huge losses in tomato yield. This research was conducted at the Egyptian Atomic Energy Authority Nuclear Research Centre. Infected plants were treated with silver nanoparticles (AgNPs). Two chemical materials, sodium borohydride and trisodium phosphate, were used for the synthesized silver nanoparticles. 1% polyvinylpyridine (PVP) was used as a stabilizer agent. AgNPs were exposed to several doses of gamma irradiation (0, 1.5, 3, 6, 12, and 24) kilo Gray (kGy) in order to enhance and maximize the effect of AgNPs on Alternaria solani. UV–Vis spectroscopy (UV), Fourier-transform infrared spectroscopy (FTIR), and transmission electron microscopy (TEM) were used to characterize AgNPs; sodium borohydride and trisodium citrate were used for the chemical reduction. AgNPs and AgNPs + gamma irradiation led to increases in shoot fresh weight and shoot dry weight; they also elevated the antioxidant enzymes, as well as peroxides and catalase, when compared with control (untreated) plants. AgNPs and AgNPs + gamma irradiation decreased the disease severity compared with the control untreated. Our study not only corroborates established trends in nano-agriculture but also introduces novel insights into the specific effects of gamma irradiation on AgNP that led to a decrease in this size in the quantum dot range (3–10) nm, as shown in Tem. By drawing parallels with the work of esteemed researchers in the field.

Dose Rate Calibration of β Radiation Source in Risø TL/OSL-DA-20 Reader Device

This research is focused on determining the dose rate calibration of beta irradiation source in the Risø brand TL/OSL-DA-20 model thermoluminescence (TL) and optically stimulated luminescence (OSL) reader device manufactured by DTU Physics which is an integral component of the Technical University of Denmark (DTU). The beta radiation source of this device comprises a pellet-shaped Strontium ceramic made from the 90Sr/90Y radionuclide, with a half-life of approximately 29.1 years. This investigation provides a thorough examination of reproducing equivalent dose levels by comparing reproduced OSL signals with the OSL signals of calibration quartz crystals which were previously exposed to a 5 Gy beta radiation emission. Throughout this process, dose durations and equivalent dose levels were analysed on optically stimulated luminescence signals. The collected OSL data aims to ensure the precise calibration of the radioactive source, contributing to reliable results in dosimetric measurements. This calibrated device is utilized in the Luminescence Laboratory co-run by the Physics Department and Nuclear Materials Research and Application Center of Selçuk University. The determined dose rate of the beta radiation source is found as 0.065 Gy/second.

Application of cyanobacteria in radioactive waste

The extremely toxic radioactive wastes whose radioactivity persists for thousands of years are accumulated through nuclear power plants, mining companies, industries, and research centers, among others. However, the lack of technology for the treatment and removal of radioactivity from radioactive waste becomes a bottleneck for research. Currently, there are temporary solutions, and the radioactive waste continues to increase. Given this scenario it is necessary to seek alternatives for the treatment of radioactive waste with efficiency and low cost, without polluting the environment, and that is not harmful to human health. One way to reduce this type of pollution is to use microorganisms, especially cyanobacteria, which comprise one of the largest, most ecologically diverse, successful, and important group of bacteria on Earth. These bacteria have a great ability to remove pollutants, such as heavy metals, textile dyes, pesticides, etc., but their role in the degradation of recalcitrant and radioactive compounds is still scarce. The present work aimed to investigate the potential of cyanobacteria isolated from different environments to remove radiolabeled molecules from radioactive waste (containing 14C radioisotopes). Seven cyanobacteria, Synechococcus sp. CENA136 (isolated from the Mangrove of Cardoso Island), Phormidium autumnale UTEX 1580 (collection of UTEX cultures - fish aquarium), Nostoc sp CENA420 (Antarctica), Limnothrix sp. CENA458 (isolated from the reservoir), Oscillatoria acuminata CENA525 (isolated from the Pantanal), Nodularia sp CENA215 (isolated from Caatinga), and Trichormus SP UFV-56 (isolated from the Federal University of Viçosa-MG) were used in the present study. Cyanobacteria were maintained in Z8, BG-11, and SWBG-11 liquid culture medium under constant fluorescent lighting of 40 µmol photons·m-2·s-1 and a controlled temperature of 23 ± 1°C. Radioactive waste containing several 14C organic molecules, solubilized in organic solvents was used. The inoculums were obtained from 50 mL of culture medium. The radioactive waste was added at concentrations of 0, 5, 10 and 15%. To investigate the removal of the radioactivity present in the waste, analysis was performed by Liquid Scintillation Counting (LSC) in the beginning and final cultivation and HPLC (coupled to a flow scintillation analyzer) in order to evaluate the profile of radioactive molecules present in the waste. Intracellularly accumulated radioactivity was also assessed by LSC after cell disruption. The ability to accumulate radioactive molecules intracellularly was observed in all cyanobacteria, but Nostoc sp CENA420 accumulated 43% and Trichormus sp UFV-56 accumulated 68%, both cultivated with 15% of radioactive waste. These results showed that the cyanobacteria Nostoc sp CENA420 and Trichormus sp UFV-56 consumed 87 and 86% of radioactive molecules, respectively, being of great potential for the removal of radiolabeled radioactive waste molecules. Research using cyanobacteria to remove radiolabeled molecules from radioactive waste is still at an early stage but is a promising alternative to biological treatment.

Production of [formula omitted]Xe and [formula omitted]Xe via neutron activation of 128Xe and 130Xe at ILL-RHF and NCBJ-MARIA high-flux reactors

The long-lived xenon isomers 129mXe and 131mXe are of interest for the GAMMA-MRI project, which aims at developing a novel imaging modality based on magnetic resonance of polarized unstable tracers. Here, we present the steps leading to and following the production of these two isomers via neutron irradiation of highly-enriched 128Xe and 130Xe gas samples at two high-flux reactors, the High-Flux Reactor (Réacteur à haut flux, RHF) at the Institut Laue-Langevin (ILL) and the MARIA reactor at the National Centre for Nuclear Research (NCBJ). We describe the experimental setups and procedures used to prepare the stable xenon samples, to open the irradiated samples, and to transfer xenon isomers into reusable transport vials. The activity of 129mXe and 131mXe was measured to be in the range of tens of MBq per sample of 0.8(1)mg, and was proportional to thermal neutron flux density. A small activity of unstable contaminants was also visible in the samples, but their level is not limiting for the GAMMA-MRI project’s objectives. In addition, the minimum thermal neutron flux density required to produce 129mXe and 131mXe sufficient for the project could be also determined.

Академич Н.Содномын мэндэлсний 100 жилийн ойд зориулсан “Рентген шинжилгээ” олон улсын эрдэм шинжилгээний зургаадугаар хурал

The Nuclear Research Center organized the sixth international conference on "X-ray Analysis" on August 28-30, 2023. The conference took place in a hybrid format, combining in-person and virtually. More than 60 scientists from Mongolia, Russia, Japan, the USA, Spain, Italy, India, and Argentina participated in the conference. The conference featured 24 oral presentations and 14 poster presentations covering both fundamental and applied research. These presentations delved into the latest developments in X-ray analysis, current trends, theoretical and methodological calculations, as well as applications in the fields of environment, geology, mining, substance structure, and radiation processing. This review article provides a summary of the significant and interesting presentations delivered at the conference

Implementation Status of Myrrha Phase 1 (Minerva)

The MYRRHA design for an accelerator driven system (ADS) is based on a 4 mA, 600 MeV CW superconducting proton linac. The construction of the first stage (called MINERVA) by the Belgium Nuclear Research Centre SCK CEN was approved in 2018. It consists of a 100 MeV superconducting RF linac as well as two independent target stations, one for radio-isotope research and production of radio-isotopes for medical purposes, the other one for fusion materials research. This contribution presents the main design choices and current status of the overall project parts (civil engineering, particle accelerator and target facilities)

Benchmarking of the SPERT-III E-core experiment with the Monte Carlo codes TRIPOLI-4®, TRIPOLI-5® and OpenMC

This paper presents a code-to-code verification of the SPERT-III reactor in its E-core configuration using the Monte Carlo codes TRIPOLI-4®, TRIPOLI-5® and OpenMC. A SPERT-III E-core model was originally developed for the Monte Carlo code TRIPOLI-4® and will be the baseline of our analysis The simulation results obtained for the main reactor physics parameters (neutron effective multiplication factor, rod worth, reactivity coefficients and kinetics parameters) with TRIPOLI-4®and OpenMC using different nuclear data libraries are compared and analyzed. Additional verifications are carried out with the next-generation Monte Carlo code TRIPOLI-5®, which is currently under development by CEA and IRSN (France). This paper summarizes a joint study that was conducted within an international research collaboration between CEA Paris-Saclay (France) and the Nuclear Research Center Negev (NRCN, Israel), and is a stepping stone towards future multi-physics simulations exploring the SPERT-III reactor power excursions, including thermal-hydraulics feedback.

New Electromagnetic Threat Protection Systems

The issues discussed in the article refer to a new category of military operations - electronic warfare (EW). In the context of EW, the high-power microwave (HPM) technology currently enables remote disturbances of operations lasting until the circuit is reset or the electronic system is destroyed. The article examines the problem of protection and defence against using HPM pulses. The research used a compact HPM generator developed at the Polish National Centre for Nuclear Research. It has a power of 3MW, an operating frequency of 2.9 GHz and a 3 μs pulse duration, emitted with a repetition rate of 1, 50, 100 and 250 Hz. The developed HPM pulse protection systems were subjected to intense field exposure in the open space of the training ground, in its land and sea sections, and in the circuit with a reverberation chamber. The distribution of the generated field on each measurement station was tested using a high-power D-dot probe, from which the data was transferred to the recording system via an optical fibre link. In all cases, this distribution turned out to be repetitive. The field probe with a logger was used for measurements inside composite structures. Unprotected electronic systems in hobby drones, mobile phones, cameras and systems using sensors based on micro-mechanical units were exposed. An analysis was conducted to check the operation of electronic circuits, effects caused and phenomena occurring during exposures to intense microwave radiation. It was found that the developed system meets the design assumptions in conditions similar to actual exposure to HPM weapons. Screening efficiency has been determined for various spatial configurations of radiation beam incidence. The presented systems for the protection and defence against the effects of HPM weapons implemented in the technology of composite hybrid absorbers enable effective elimination of electromagnetic pulse effects.

THE EXOGAM2 CALIBRATION USING THE NEWLY DEVELOPED NUMEXO2 DIGITAL ELECTRONIC

In this study, the calibration process of the EXOGAM2 conventional gamma detector system with the newly developed digital electronic device, namely NUMEXO2, will be presented. This experimental study was performed at the GANIL (Grand Accélérateur National d'Ions Lourds) nuclear research center in France. The energy calibration of the EXOGAM2 detector system with the newly developed NUMEXO2 digital electronic device was conducted using both low and high gamma energy levels of a 152Eu radioactive source. This calibration was carried out for two EXOGAM2 detectors, and the energy resolution of each crystal in the EXOGAM2 system was determined. 
 The energy resolution of each crystal was found to be reasonable energy resolution values of the EXOGAM2 detectors. Therefore, the use of the digital electronic device NUMEXO2 did not affect the energy resolution of the detectors, but it did enable us to acquire data at a high counting rate.

Contributions of MYRRHA to the European Fusion Energy Roadmap

One of the main objectives of the EUROfusion Roadmap to Fusion Energy during Horizon Europe is to finalize the conceptual design (thus preparing the engineering design phase) and initiate the construction of a fusion spectrum neutron source (IFMIF-DONES). The Belgian Nuclear Research Center is currently developing the MYRRHA research facilities, which include a subcritical accelerator-driven system ignited by a 600 MeV superconducting linear proton accelerator coupled to a 100 MeV proton injector. The implementation of the multipurpose fast spectrum reactor MYRRHA will proceed in phases, with phase I, covering 2019–2027, including the deployment of the 100 MeV proton accelerator and associated fusion material research facilities. The research on fusion materials on the basis of the 100 MeV proton beam and with hot cell facilities will focus on innovative materials and composites and will be fully complementary to IFMIF-DONES as well to the planned research program on using currently available nuclearized facilities such as BR2 (Belgian Research Reactor 2) and Hot Cells for mechanical, microstructural and chemical analysis. A bespoke fusion irradiation module is also foreseen on the MYRRHA reactor, the construction of which is planned in the third phase of the implementation of the project (i.e. after 2035). Provisions have been made in the core of the MYRRHA reactor to include so-called In-Pile Sections around the central core or at the central core position below the spallation target when operating in subcritical mode. In this contribution, we review the role and technical capabilities that MYRRHA facilities may provide in the framework of the European Fusion Electricity Roadmap and specifically for DEMO Engineering Design, Material's Development and enhancement of Technology Readiness Level. Aspects of education and training, being an integral part of the European nuclear fusion program, are also touched upon. Finally, the synchronization of the timelines for the implementation of MYRRHA and the EU fusion facilities are discussed.

Initial approach to application of gamma spectroscopy to alpha particles dosimetry in BNCT.

The aim of the study is to show a method of real-time determination of the dose deposited in a tissue-like medium by α-particles emitted from the 10B(n,α)7Li reaction. The applied research method is to determine the correlation between the measured density of α-particle traces and measured in real time the 478keV prompt-gamma rays derived from the 10B(n,α)7Li reaction. To achieve this aim, an appropriate construction of an experimental set-up is needed. The experimental set-up built for the purpose of the measurements carried out in the MARIA Reactor at the National Centre for Nuclear Research in Świerk, Poland, is presented. The main challenges related to obtaining optimal conditions for the measurement of the 478keV gamma photons; the preliminary results of spectrometric measurements and further studies are also discussed.