1 Activation Analysis A comparison between FLUKA and FISPACT results Pavia, 16 - 12 - 2014 Gabriele Firpo Reactor and Safety Dept. Phone: +39.010.655.83.42.

Slides:



Advertisements
Similar presentations
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 HW 14 More on Moderators Calculate the moderating power and ratio for pure D 2 O as well.
Advertisements

NDVCS measurement with BoNuS RTPC M. Osipenko December 2, 2009, CLAS12 Central Detector Collaboration meeting.
Stefan Roesler SC-RP/CERN on behalf of the CERN-SLAC RP Collaboration
EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.
Modeling of Photonuclear Reactions & Transmutation of Long-lived Nuclear Waste in High Photon Fluxes M.-L. GIACRI-MAUBORGNE, D. RIDIKAS, J.-C.
Neutron background measurements at LNGS Gian Luca Raselli INFN - Pavia JRA1 meeting, Paris 14 Feb
Using FLUKA to study Radiation Fields in ERL Components Jason E. Andrews, University of Washington Vaclav Kostroun, Mentor.
Pion yield studies for proton drive beams of 2-8 GeV kinetic energy for stopped muon and low-energy muon decay experiments Sergei Striganov Fermilab Workshop.
Case Monte Carlo Simulations 4/17/2008. Toolbox MCNP5 – the grunt work Polimi – low energy stuff Matlab – post processing.
Target Activation Study Paul Hodgson The University of Sheffield.
Radiation Dosimetry Dose Calculations D, LET & H can frequently be obtained reliably by calculations: Alpha & low – Energy Beta Emitters Distributed in.
Optical Fibre Dosimetry First Thoughts. Goal Target Measuring dose in a distributed way using optical fibres (“active”) Constraints: – Mixed-Radiation.
Radiation therapy is based on the exposure of malign tumor cells to significant but well localized doses of radiation to destroy the tumor cells. The.
Basic Lecture I: Geometry and Source Definition
Sergey Ananko Saint-Petersburg State University Department of Physics
NEEP 541 Radiation Interactions Fall 2003 Jake Blanchard.
Status and needs of activation data for fusion Robin Forrest 1 and Jura Kopecky 2 1 Euratom/UKAEA Fusion Association Culham Science Centre, UK 2 JUKO Research,
Using FLUKA for radioactive waste zoning L. Nicolas, FLUKA meeting, March
ELI-NP: the way ahead, March Anna Ferrari An overview of the shielding problems around high energy laser-accelerated beams Anna Ferrari Institute.
Future usage of quasi-infinite depleted uranium target (BURAN) for benchmark studies Pavel Tichý Future usage of quasi-infinite depleted uranium target.
1 Dr. Sandro Sandri (President of Italian Association of Radiation Protection, AIRP) Head, Radiation Protection Laboratory, IRP FUAC Frascati ENEA – Radiation.
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom Status of Neutronics Tools & Data for IFMIF-EVEDA U. Fischer, S. Simakov.
Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination.
If the Coordinates system is. R r b (impact parameter.
Normalisation modelling sources Geant4 tutorial Paris, 4-8 June 2007 Giovanni Santin ESA / ESTEC Rhea System SA.
Event generator comparison Zhiwen Zhao 2013/12/03 original 2014/02/12 update 2014/11/04 update.
Cosmic-Ray Induced Neutrons: Recent Results from the Atmospheric Ionizing Radiation Measurements Aboard an ER-2 Airplane P. Goldhagen 1, J.M. Clem 2, J.W.
The propagation of a microwave in an atmospheric pressure plasma layer: 1 and 2 dimensional numerical solutions Conference on Computation Physics-2006.
Radiation damage calculation in PHITS
Y. Romanets 1, R. Luis 1,J. Bermudez 3, J.C. David 5, D. Ene 5, I. F. Goncalves 1, Y. Kadi 2, C. Kharoua 2, F. Negoita 4, R. Rocca 2, L. Tecchio 3, P.
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.
Cross-sections of Neutron Threshold Reactions Studied by Activation Method Nuclear Physics Institute, Academy of Sciences of Czech Republic Department.
1 Scale Detection in Geothermal Systems The use of nuclear monitoring techniques E. Stamatakis a,b, T. Bjørnstad b, C. Chatzichristos b, J. Muller b and.
Neutron production study with the thick lead target and uranium blanket irradiated by 1.5 GeV protons Filip Křížek, ÚJF AV ČR.
Effects of long term annealing in p-type strip detectors irradiated with neutrons to Φ eq =1·10 16 cm -2, investigated by Edge-TCT V. Cindro 1, G. Kramberger.
P HI T S Setting of various source Part I Multi-Purpose Particle and Heavy Ion Transport code System Title1 Aug revised.
Experimental Studies of Spatial Distributions of Neutrons Produced by Set-ups with Thick Lead Target Irradiated by Relativistic Protons Vladimír Wagner.
Initial (FLUKA) calculations for synchrotron radiation at TLep April 4 th, 2013 F. Cerutti, A. Ferrari, L. Lari* *BE Dept.
Cristian Bungau ThorEA Meeting - Oxford - April 2010.
Workshop On Nuclear Data for Advanced Reactor Technologies, ICTP , A. Borella1 Monte Carlo methods.
FLUKA Meeting Milan Jul 2010 Work in the frame of the LHC Phase II Upgrade Previous work was dedicated to the study of the.
ANITA workshop, Uppsala, december 2008 ANITA neutron source Monte Carlo simulations and comparison with experimental data Mitja Majerle Nuclear Physics.
Risk Analysis P. Cennini AB-ATB on behalf of the n_TOF Team  Procedure  Documents in preparation  Conclusions Second n_TOF External Panel Review, CERN,
Ondřej Svoboda Nuclear Physics Institute, Academy of Sciences of Czech Republic Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical.
Neutron production in Pb/U assembly irradiated by deuterons at 1.6 and 2.52 GeV Ondřej Svoboda Nuclear Physics Institute, Academy of Sciences of Czech.
1 Neutron Effective Dose calculation behind Concrete Shielding of Charge Particle Accelerators with Energy up to 100 MeV V. E Aleinikov, L. G. Beskrovnaja,
HTS Tl-based coatings for FCC beam screens - Radiation Protection Aspects - Markus WIDORSKI, DGS-RP Information on ActiWiz: Courtesy of Chris Theis, DGS-RP.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Modern , d, p, n-Induced Activation Transmutation Systems EURATOM/CCFE.
Radiation protection and radiation safety issues for HIE-ISOLDE. FLUKA calculations Y. Romanets ISOLDE Workshop and Users meeting 2010 CERN, 8 December.
Systematic limitations to luminosity determination in the LumiCal acceptance from beam-beam effects C. Rimbault, LAL Orsay LCWS06, Bangalore, 9-13 March.
A. Dokhane, PHYS487, KSU, 2008 Chapter1- Neutron Reactions 1 NEWS Lecture1: Chapter 0 is already on my Website.
Marina Golubeva, Alexander Ivashkin Institute for Nuclear Research RAS, Moscow AGeV simulations with Geant4 and Shield Geant4 with Dpmjet-2.5 interface.
1 Simulation of Neutron Backgrounds in the ILC Extraction Line Beam Dump Siva Darbha Supervisors: Lewis Keller and Takashi Maruyama.
1 Giuseppe G. Daquino 26 th January 2005 SoFTware Development for Experiments Group Physics Department, CERN Background radiation studies using Geant4.
AWAKE: D2E for Alexey beam properties Silvia Cipiccia, Eduard Feldbaumer, Helmut Vincke DGS/RP.
4th International Summer School « Nuclear Physics Methods and Accelerators in Biology and Medicine » Monte-Carlo simulations : FLUKA vs. MCNPX Maxime ODEN.
1 G. Cambi, D.G. Cepraga, M. Frisoni Enea & Bologna University Team OSIRIS neutronic and activation simulation with Scalenea-ANITA in support of PACTITER/CORELE.
Ali Ahmad FLUKA code validation of nuclear data required for the spallation target design in Accelerator Driven Subcritical Reactors ThorEA Meeting – Daresbury.
Monte Carlo methods in spallation experiments Defense of the phD thesis Mitja Majerle “Phasotron” and “Energy Plus Transmutation” setups (schematic drawings)
RHD-DoPET CNAO test beam result (may 2014)
Decay Data for Fusion Applications: Status, Issues and Needs
Measurements and FLUKA Simulations of Bismuth and Aluminum Activation at the CERN Shielding Benchmark Facility(CSBF) E. Iliopoulou, R. Froeschl, M. Brugger,
Bayesian Monte-Carlo and Experimental Uncertainties
γ γ-> hadron Background Events at CLIC
for collaboration “Energy plus transmutation”
Setting of various sources A
Simulation of Neutron Backgrounds in the ILC Extraction Line Beam Dump
Performed experiments Nuclotron – set up ENERGY PLUS TRANSMUTATION
Neutron production in Pb/U assembly irradiated by p+, d+ at 0. 7 – 2
Presentation transcript:

1 Activation Analysis A comparison between FLUKA and FISPACT results Pavia, Gabriele Firpo Reactor and Safety Dept. Phone:

2 Background – The Activation Analysis approach in: FLUKA FISPACT Comparison between FLUKA and FISPACT calculations: Methodology Results Summary and Conclusions CONTENT Pavia,

3 DEFINITION Activation Analysis In the framework of this presentation, it is intended as, and limited to: The evaluation of the total activity concentration of a material slab being irradiated by monoenergetic projectile particles. The evaluation of other physical quantities, related to the «activation analysis» as typically intended, like: Nuclide inventories at different cooling times; Corresponding radiation fields following the material activation are actually foreseen as a FLUKA/FISPACT comparison issue, but they are out of scope of the present analysis. BACKGROUND The Bateman Equations Pavia,

4 BACKGROUND THE ACTIVATION ANALYSIS APPROACH IN FLUKA AND FISPACT ItemFISPACTFLUKA MethodNumerical Solution of Bateman Equations Full Monte Carlo approach; «Mixed» Monte Carlo/Analytical solution of Bateman Equations. Geometry0-D approach*Full 3-D approach* Parameters of Bateman Equations Evaluated Data (EAF libraries) Evaluated Data / Models** LimitationsNo build-up No self-shielding No build-up * = See next slide **= Depending on the projectile type/energy Pavia,

5 BACKGROUND Homogeneous and isotropic irradiating flux; No flux attenuation: The effective volume/mass is just a normalization factor. «Real» irradiating flux profile; Flux attenuation: The effective volume/mass and dimensions do impact on the activation results. Φ x 0-D approach (FISPACT)3-D approach (FLUKA) Pavia,

6 PROBLEM In order to compare FLUKA and FISPACT approaches, the problem is: How to make a 0-D (FISPACT) geometrical approach equivalent to a 3-D (FLUKA) one? Pavia,

7 SOLUTION METHODOLOGY Noting that: The 0-D (FISPACT) approach is rigid: no «degrees of freedom» to reproduce any kind of irradiating scenario; The 3-D (FLUKA) approach lets the user to define any kind of irradiating scenario; many «degrees of freedom» to define it also «whatever the user likes». It is then envisaged to: 1.Define an irradiating scenario—in principle, as simple as possible—suitable for the 0-D (FISPACT) approach; 2.Define, consequently, the corresponding and equivalent irradiation scenario in FLUKA. HOW? Let’s see a practical example… Pavia,

8 METHODOLOGY 1.Fill the list of parameters to completely define a 0-D irradiation scenario in the FISPACT input files: Particle type t and energy E; Homogeneous and isotropic flux Φ; Material Mat with Volume V (or Mass M); Irradiation time(s) T i ; Cooling time(s) C i. 2.Fill the equivalent FLUKA/FLAIR «decay» input file as follow: Define an extended isotropic source of particle t with energy E; the source region must correspond to the detector region; Define the material Mat with volume V in the detector region; Define the IRRPROFI and DCYTIMES cards with the irradiation parameters T i and C i. In particular, the beam intensity— WHAT(2),(4),(6) of the IRRPROFI card—must be equal to the number of particle/s causing an average total flux equal to Φ. This value can be evaluated by another dedicated FLUKA run with USRTRACK card. OPERATIVE EXAMPLE Pavia,

9 CONSIDERED SCENARIOS METHODOLOGY Case IDParticle type EnergyFluxTarget geom. MaterialIrrad. Time Cooling times 1Proton50 MeV 1E8 p/cm 2 /s Cylinder (r=1 cm, h=1 µm) SS316LN90 days0 s 2Proton20 MeV 1E8 p/cm 2 /s Cube (1x1x1 cm 3 ) SS316LN15 years From 0 s up to 20y 3Neutron50 MeV 1E8 n/cm 2 /s Cylinder (r=1 cm, h=1 µm) SS316LN90 days0 s 4Neutron50 MeV 1E8 n/cm 2 /s Cylinder (r=1 cm, h=50 cm) SS316LN90 days0 s 5NeutronThermal 1E8 n/cm 2 /s Cube (1x1x1 cm 3 ) Cobalt90 days0 s 6NeutronThermal 1E8 n/cm 2 /s Cube (1x1x1 cm 3 ) SS316LN15 years From 0 s up to 20y Note 2: Only neutrons, protons and deuterons projectiles with energies from 0 up to ~55 MeV can be defined with FIPACT 2010 (many other particle types and higher energies, up to ~1 GeV, are available in FISPACT II by CCFE). Note 1: Available code versions: FISPACT 2010, FLUKA b trial. Pavia,

10 Case IDTotal activity concentration [Bq/cm 3 ] Ratio FLUKA/ FISPACT FLUKAFISPACT 13.35E61.86E See graph in the next slide 0.46 (average) 31.55E61.22E E51.22E E84.72E See graph in the next slide 1.83 (average) RESULTS Pavia,

11 RESULTS Pavia,

12 A methodology to make FISPACT and FLUKA activation calculations comparable has been setup; Several test runs have been perfomed, showing compatible results within a factor of a few. SUMMARY And CONCLUSIONS Pavia,

13 The phase space of the irradiation scenario parameters has many dimensions: sensitivity analyses are envisaged to understand/find correlations (if any); For example, it is expected that, as the linear dimensions of the material slab increase becoming larger than the mean free path of the projectile particle, the effect of flux attenuation in energy becomes not negligible. HINTS QUESTIONS? COMMENTS? Pavia,

14 MANY THANKS FOR YOUR ATTENTION Pavia,