A5054430402- Boron Compounds in Chemistry
- Nuclear Physics and Applications
- Boron and Carbon Nanomaterials Research
- Radiation Therapy and Dosimetry
- Graphite, nuclear technology, radiation studies
- Nuclear reactor physics and engineering
- Radiation Detection and Scintillator Technologies
- Radiopharmaceutical Chemistry and Applications
- Machine Learning in Materials Science
- Medical Imaging Techniques and Applications
- Nuclear and radioactivity studies
- Advanced Radiotherapy Techniques
- Nuclear Materials and Properties
- Radioactive element chemistry and processing
- Advanced MRI Techniques and Applications
- Pharmacological Effects and Toxicity Studies
- Atomic and Subatomic Physics Research
- Superconducting Materials and Applications
- MXene and MAX Phase Materials
- Radiation Effects in Electronics
- Spacecraft and Cryogenic Technologies
- Cardiac Structural Anomalies and Repair
- Radioactive contamination and transfer
- Geophysics and Gravity Measurements
- Ferroelectric and Negative Capacitance Devices
VTT Technical Research Centre of Finland
2009-2022
Tekes
2007
Fusion Academy
2006
Fusion (United States)
2006
Valley Tech Systems (United States)
2003
University of Helsinki
1998-2001
Purpose: In this work, accuracy of themcnp5 code in the electron transport calculations and its suitability for ionization chamber (IC) response simulations photon beams are studied comparison to egsnrc penelope codes. Methods: The is by comparing depth dose distributions a water phantom subdivided into thin layers using incident energies (0.05, 0.1, 1, 10 MeV) broad parallel beams. IC three dosimetric gas materials (air, argon, methane based tissue equivalent gas) (60Co source, 6 MV linear...
The response of alanine solid state dosimeters to ionizing radiation strongly depends on particle type and energy. Due nuclear interactions, neutron fields usually also consist secondary particles such as photons protons diverse energies. Various experiments have been carried out in three different beams explore the dose behavior validate model predictions. Additionally, application medical for boron capture therapy is discussed.Alanine detectors irradiated thermal field research reactor...
Polymer gels have been reported as a new, potential tool for dosimetry in mixed neutron–gamma radiation fields. In this work, BANG-3 (MGS Research Inc.) gel vials from three production batches were irradiated with 6 MV photons of Varian Clinac 2100 C linear accelerator and the epithermal neutron beam Finnish boron capture therapy (BNCT) facility at FiR 1 nuclear reactor. The is tissue equivalent main elemental composition density its T2 relaxation time dependent on absorbed dose. map was...
An international collaboration was organized to undertake a dosimetry exchange enable the future combination of clinical data from different centers conducting neutron capture therapy trials. As first step (Part I) group Americas, represented by MIT, visited at Studsvik (Sweden), VTT Espoo (Finland), and Nuclear Research Institute (NRI) Rez (Czech Republic). A combined VTT/NRI reciprocated with visit MIT. Each participant performed series measurements under equivalent irradiation conditions...
Radiation-sensitive polymer gels are among the most promising three-dimensional dose verification tools developed to date. We tested normoxic gel dosimeter known by acronym MAGIC (methacrylic and ascorbic acid in gelatin initiated copper) evaluate its use boron neutron capture therapy (BNCT) dosimetry. irradiated a large cylindrical phantom (diameter: 10 cm; length: 20 cm) epithermal beam of Finnish BNCT facility at FiR 1 nuclear reactor. Neutron irradiation was simulated with Monte Carlo...
Purpose: The most commonly used technology currently for autoradiography is storage phosphor screens, which has many benefits such as a large field of view but lacks particle‐counting detection the time and energy each detected radionuclide decay. A number alternative designs, using either solid state or scintillator detectors, have been developed to address these issues. aim this study characterize imaging performance one instrument, double‐sided silicon strip detector (DSSD) system digital...
AbstractThe objective of the study has been to estimate residual activity in decommissioning waste TRIGA Mark II–type research reactor FiR 1 Finland. Neutron flux distributions were calculated with Monte Carlo code MCNP. These used ORIGEN-S point-depletion calculate neutron-induced materials at different time points by modeling irradiation history and radioactive decay. Knowledge inventory irradiated is important planning activities essential for predicting radiological impact personnel...
Abstract Iodine is one of the most radiotoxic fission product released from fuel during a severe nuclear power plant accident. Within containment building, iodine compounds can react e.g. on painted surfaces and form gaseous organic iodides. In this study, it was found out that methyl iodide (CH 3 I) oxidised when exposed to beta radiation in an oxygen containing atmosphere. As result, nucleation aerosol particles takes place formation oxide suggested. These are highly hygroscopic. They take...
Dose planning in boron neutron capture therapy (BNCT) is a complex problem and requires sophisticated numerical methods. In the framework of Finnish BNCT project, new deterministic three‐dimensional radiation transport code MultiTrans has been developed at VTT Chemical Technology, based on novel application tree multigrid technique. To test applicability this realistic dose problem, cylindrical PMMA (polymethyl‐methacrylate) phantom was chosen as benchmark case. It convenient benchmark, it...
In this paper, the accuracy of dose planning calculations for boron neutron capture therapy (BNCT) brain and head neck cancer was studied at FiR 1 epithermal beam. A cylindrical water phantom an anthropomorphic were applied with two beam aperture-to-surface distances (ASD). The using simulation environment radiation application (SERA) treatment system compared to activation measurements Au Mn foils, photon ionization chamber reference simulations MCNP5 code. Photon SERA differ from by 2–13%...
Incineration of spent ion exchange resin was simulated using the ChemSheet chemical calculation program. The simulation incineration modeled for typical produced by pressurized water reactors (PWRs) and boiling (BWRs) in Finland. objective study to find volume mass reduction compounds formed during incineration. showed that active elements did not play any role owing small amount Cs, Co, etc. ash contained metal oxides—mainly hematite, iron oxide Fe2O3. Other products were water, carbon...
Calculation of neutron flux in three-dimensions is a complex problem. A novel approach for solving complicated transport problems presented, based on the tree multigrid technique and Simplified P3 (SP3) approximation. Discretization second-order elliptic SP3 equations performed regular three-dimensional octree grid by using an integrated scheme. The generated directly from STL files, which can be exported practically all computer-aided design-systems. Marshak-like boundary conditions are...