Albert Riego, Guillem Cortes, Francisco Calviño July 22 th, 2015 Universitat Politecnica de Catalunya, Barcelona (Spain) Third BRIKEN WORKSHOP – IFIC (Valencia,

Slides:



Advertisements
Similar presentations
Neutron detectors and spectrometers 1) Complicated reactions → strong dependency of efficiency on energy 2) Small efficiency → necessity of large volumes.
Advertisements

ROGER CABALLERO-FOLCH Universitat Politècnica de Catalunya 26 de febrer de 2013 NUSTAR ANNUAL MEETING GSI Darmstadt, Germany Beta dELayEd Neutron.
EAR2 simulation update Collaboration board meeting Christina Weiss & Vasilis Vlachoudis.
ROGER CABALLERO FOLCH, Barcelona, 9 th November 2011.
MONTE-CARLO TECHNIQUES APPLIED TO PROTON DOSIMETRY AND RADIATION SAFETY F. Guillaume, G. Rucka, J. Hérault, N. Iborra, P. Chauvel 1 XXXV European Cyclotron.
OVERVIEW NEDA Introduction to the Simulations – Geometry The Simulations Conclusions 3.7% This work summarizes the introduction to the simulations of.
Neutron energy spectrum from U and Th traces in the Modane rock simulated with SOURCES (full line). The fission contribution is also shown (dashed line).
HYDRODYNAMIC EVOLUTION OF IFE CHAMBERS WITH DIFFERENT PROTECTIVE GASES AND PRE-IGNITION CONDITIONS Zoran Dragojlovic and Farrokh Najmabadi University of.
Tissue inhomogeneities in Monte Carlo treatment planning for proton therapy L. Beaulieu 1, M. Bazalova 2,3, C. Furstoss 4, F. Verhaegen 2,5 (1) Centre.
Design on Target and Moderator of X- band Compact Electron Linac Neutron Source for Short Pulsed Neutrons Kazuhiro Tagi.
Rn Diffusion In Polyethylene Wolfgang Rau Queen’s University Kingston  Motivation  Experimental Setup – Diffusion Model  Measurement – Efficiency Simulation.
Joint IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies Student’s presentation Calculation of correction factors for neutron.
Abstract A time resolved radial profile neutron diagnostic is being designed for the National Spherical Torus Experiment (NSTX). The design goal is to.
Design of the Photon Collimators for the ILC Positron Helical Undulator Adriana Bungau The University of Manchester Positron Source Meeting, July 2008.
Monte Carlo Study to determine the Neutron Fluence spectrum for a water Phantom: Preliminary Results University of the Western Cape Energy Postgraduate.
Future usage of quasi-infinite depleted uranium target (BURAN) for benchmark studies Pavel Tichý Future usage of quasi-infinite depleted uranium target.
GEANT Study of Electron ID and  0 Rejection for Containerized detectors Compare detectors in shipping containers to idealized continuous detector with.
Monte Carlo simulation of liquid scintillation neutron detectors: BC501 vs. BC537 J.L. Tain Instituto de Física Corpuscular C.S.I.C - Univ.
1 Dr. Sandro Sandri (President of Italian Association of Radiation Protection, AIRP) Head, Radiation Protection Laboratory, IRP FUAC Frascati ENEA – Radiation.
Setups (BELEN, MONSTER  D. Cano-Ott/ CIEMAT) Implantation detector (SIMBA, AIDA (>autumn 2010) ) Beams N=50 (78Ni): 124Sn (?) N=82 (132Sn, 130Cd): 136Xe,
Ciemat Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas D. Cano-Ott DESPEC/HISPEC Coll. Meeting, 15th-16th of June 2005-Valencia.
Development of the neutron counters for the Spin dipole resonance Kazuhiro Ishikawa.
Tungsten Calorimeter Model Calculations and Radiation Issues Pavel Degtiarenko Radiation Control Group, Jefferson Lab.
Monte Carlo simulations of a first prototype micropattern gas detector system used for muon tomography J. B. Locke, K. Gnanvo, M. Hohlmann Department of.
M. Manolopoulou 1, M. Fragopoulou 1, S. Stoulos 1, E. Vagena 1, W. Westmeier 2, M. Zamani 1 1 School of Physics, Aristotle University of Thessaloniki,
Advanced semiconductor detectors of neutrons
Simulations on “Energy plus Transmutation” setup, 1.5 GeV Mitja Majerle
Monte Carlo methods in ADS experiments Study for state exam 2008 Mitja Majerle “Phasotron” and “Energy Plus Transmutation” setups (schematic drawings)
Systematic studies of neutrons produced in the Pb/U assembly irradiated by relativistic protons and deuterons. Vladimír Wagner Nuclear physics institute.
DESPEC A Algora IFIC (Valencia) for the Ge array working group.
Studies of Helium proportional counters response on fast neutrons, at NCSR “Demokritos” M. Zamani, M. Manolopoulou, S. Stoulos, M. Fragopoulou School of.
Applications of Monte Carlo Code for a Gamma Resonance System Analysis L. Wielopolski, A. Hanson, I. Dioszegi, M. Todosow, Brookhaven National Laboratory,
The improvement of the energy resolution in epi-thermal region of Bonner sphere using boric acid solution moderator H. Ueda1, H. Tanaka2, Y. Sakurai2.
Experimental Studies of Spatial Distributions of Neutrons Produced by Set-ups with Thick Lead Target Irradiated by Relativistic Protons Vladimír Wagner.
PNPI, R&D MUCH related activity ● Segmentation ● Simulation of the neutral background influence ● R&D of the detectors for MUCH ● Preparation to the beam.
Improvement of the Monte Carlo Simulation Efficiency of a Proton Therapy Treatment Head Based on Proton Tracking Analysis and Geometry Simplifications.
1 Possibility to obtain a polarized hydrogen molecular target Dmitriy Toporkov Budker Institute of Nuclear Physics Novosibirsk, Russia XIV International.
The PrimEx-I Beam line. A. GasparianPrimEx-II Beam Line, August 5, MC Results for the PrimEx-I configuration Beam Background on HyCal: Energy Distribution.
CERF simulation Mitsu 14th Feb Simulation components Production Transportation Detector response
Simulations on “Energy plus Transmutation” setup, 1.5 GeV Mitja Majerle, V Wagner, A Krása, F Křížek This document can be downloaded.
Neutron production in Pb/U assembly irradiated by 1.26 AGeV deuterons. First experimental results Ondřej Svoboda Neutron production in Pb/U assembly irradiated.
KIT – The cooperation of Forschungszentrum Karlsruhe GmbH and Universität Karlsruhe (TH) Institute for Neutron Physics and Reactor Technology Evaluation.
Design of novel GEM-based neutron spectrometer E. Aza 1,2* 1 CERN, 1211 Geneva, Switzerland, 2 AUTH, Department of Physics, Thessaloniki, Greece,
4th International Summer School « Nuclear Physics Methods and Accelerators in Biology and Medicine » Monte-Carlo simulations : FLUKA vs. MCNPX Maxime ODEN.
The PrimEx-I Beam line. A. GasparianPrimEx-II Beam Line, August 5, MC Results for the PrimEx-I configuration Beam Background on HyCal: Energy Distribution.
Development of a Single Ion Detector for Radiation Track Structure Studies F. Vasi, M. Casiraghi, R. Schulte, V. Bashkirov.
Optimization of Scintillators for Stacked-layer Detectors of FNGR 1,2 Jea Hyung Cho, 1,2 Kwang Hyun Kim *, and 3 Young Hyun Jung 1 Biomedical Engineering,
ESS Detector Group Seminar Edoardo Rossi 14th August 2015
3 rd BRIKEN WORKSHOP: Welcome! 3 rd BRIKEN WORKSHOP, IFIC, Valencia 22-24/07/2015 C. Domingo-Pardo IFIC (CSIC-University of Valencia)
1 Alushta 2016 CROSS SECTION OF THE 66 Zn(n,α) 63 Ni REACTION at CROSS SECTION OF THE 66 Zn(n, α) 63 Ni REACTION at E n = 4.0, 5.0 and 6.0 MeV I. Chuprakov,
2 nd BRIKEN WORKSHOP: An Overview of the Project 2 nd BRIKEN WORKSHOP, RIKEN Nishina Center 30-31/07/2013 C. Domingo-Pardo IFIC (CSIC-University of Valencia)
Optimization of Scintillators for Stacked-layer Detectors of FNGR 1,2 Jea Hyung Cho, 1,2 Kwang Hyun Kim *, and 3 Young Hyun Jung 1 Biomedical Engineering,
Air University: The Intellectual and Leadership Center of the Air Force Aim High…Fly - Fight - Win The AFIT of Today is the Air Force of Tomorrow. Muon.
Ali Ahmad FLUKA code validation of nuclear data required for the spallation target design in Accelerator Driven Subcritical Reactors ThorEA Meeting – Daresbury.
Calculation of efficiency for a high-resolution gamma-ray spectrometer used for environmental radioactivity measurements Ileana Radulescu, Marian Romeo.
Monte Carlo methods in spallation experiments Defense of the phD thesis Mitja Majerle “Phasotron” and “Energy Plus Transmutation” setups (schematic drawings)
Fast neutron flux measurement in CJPL
Validation of Geant4 against the TARC benchmark: Testing neutron production, transportation and interaction TARC – experimental set-up and aims Geant4.
Positron production rate vs incident electron beam energy for a tungsten target
P. Buffa, S. Rizzo, E. Tomarchio
Measurements and FLUKA Simulations of Bismuth and Aluminum Activation at the CERN Shielding Benchmark Facility(CSBF) E. Iliopoulou, R. Froeschl, M. Brugger,
M. Migliorati, C. Vaccarezza INFN - LNF
Inter-comparison of Particle production (2)
Development and characterization of the Detectorized Phantom for research in the field of spatial fractionated radiation therapy. D. Ramazanov, V. Pugatch,
for collaboration “Energy plus transmutation”
Arghya Chattaraj, T. Palani Selvam, D. Datta
Theme group for b-delayed neutron measurements
JOINT INSTITUTE FOR NUCLEAR RESEARCH
Local coordinator: S. Nishimura
Research Activities Seminar Nuclear Physics Group
Presentation transcript:

Albert Riego, Guillem Cortes, Francisco Calviño July 22 th, 2015 Universitat Politecnica de Catalunya, Barcelona (Spain) Third BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, 2015 BRIKEN detector: UPC Monte Carlo design compact geometry

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques Contents 1.Matrix geometry 2.Counters employed 3.Simulations 4.Results 5.Conclusions

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 1. Final matrix geometry Material -High density polyethylene -Density: 0.93 g/cm 3 Dimensions -7 concentric rings -Squared section: 1000 mm x 1000 mm -Length: 800 mm -Squared beam hole: 110 mm x 110 mm Frontal view of polyethylene matrix

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 2. Counters employed for the detector design Transversal section of polyethylene matrix. Institution Filling gas Pressure (atm) DIMENSIONS Number of counters Diameter (inch/cm) Effective length (inch/cm) GSIHe-3101 / / JINRHe / / ORNL He-3102 / / He-3101 / / RIKENHe-341 / / UPC He / /

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 3. Simulations Neutron source ̵ Point source ̵ Inside the beam hole ̵ Centered in the matrix ̵ Neutrons emitted in all directions (isotropic distribution) Neutron energies simulated ̵ MeV ̵ MeV ̵ 0.01 MeV ̵ 0.1 MeV ̵ 1 MeV ̵ 2 MeV ̵ 3 MeV ̵ 4 MeV ̵ 5 MeV Frontal view Lateral view Monte Carlo codes used -MCNPX, version 2.5 -GEANT 4, release p02 Beam hole (air) Polyethylene matrix

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 3. Simulations Goal to reach by MC simulations -Flat efficiency and high efficiency up to E n = 5 MeV

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 4. Results Contribution of each ring to the neutron detection efficiency

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 4. Results 1-neutron emission. MCNPX code GEANT4 code

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 4. Results 2 -neutron emission. MCNPX code GEANT4 code

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques 5. Conclusions -The design has been optimized for 172 He-3 counters with the properties of the counters available -We have optimized the neutron detection efficiency to obtain a high and flat efficiency -Polyethylene matrix of 100 cm x 100 cm and 80 cm length for neutron moderation -We have employed 172 He-3 counters at different pressures, diameters and length -He-3 counters distributed in 7 concentric rings -The geometry is based on cylindric symmetry -The simulations have been done by means of MCNX an GEANT4 codes -The mean efficiencies and efficiency factors for 1-n emission are: -Max neutron energy of 1 MeV: η = 67.8 % & F= Max neutron energy of 3 MeV: η = 67.2 % & F= Max neutron energy of 5 MeV: η = 66.0 % & F= The mean efficiencies and efficiency factors for 2-n emission are: -Max neutron energy of 1 MeV: η = 70.6 % & F= Max neutron energy of 3 MeV: η = 70.2 % & F= Max neutron energy of 5 MeV: η = 69.0 % & F= Possibility to define new geometries to optimize the neutron detection efficiency for higher neutron energies than 5 MeV -Possibility to optimize the geometries shown in this presentation to increase the mean efficiency

3 rd BRIKEN WORKSHOP – IFIC (Valencia, Spain) / July 22-24, /11 Department of Physics and Nuclear Engineering / Institut de Tècniques Energètiques Thank you for your attention