THE ROLE OF CORRELATIONS IN MONTE CARLO CRITICALITY SIMULATIONS
|
|
- Derick Cain
- 5 years ago
- Views:
Transcription
1 THE ROLE OF CORRELATIONS IN MONTE CARLO CRITICALITY SIMULATIONS ANDREA ZOIA CEA/SACLAY Séminaire MANON Andrea ZOIA DEN/DANS/DM2S/SERMA/LTSD March 22nd 2016 APRILE 13, 2016 PAGE 1
2 OUTLINE q Power iteragon with Monte Carlo q The impact of correlagons in crigcality simulagons q Entropy and convergence q SpaGal moments and correlagons q RelaGon to neutron clustering theory q PerspecGves CEA March 22nd 2016 PAGE 2
3 THE CRITICAL BOLTZMANN EQUATION We would like to determine q the fundamental mode ϕ 1 q and the associated fundamental eigenvalue k 1 of Critical Boltzmann equation for the neutron flux ϕ Net disappearance operator L Creation (fission) operator F CEA March 22nd 2016 PAGE 3
4 POWER ITERATION A generalized eigenvalue equation Power iteration algorithm: q Guess solution q Iterate Hypothesis Convergence CEA March 22nd 2016 PAGE 4
5 MONTE CARLO APPROACH: CRITICALITY SIMULATION 1 st gen. 2 nd gen. 3 rd gen. 4 th gen. 5 th gen. Source Fission chain t Source 1 st gen. 2 nd gen. 3 rd gen. N 0 particles Fission generations CEA March 22nd 2016 PAGE 5
6 POWER ITERATION: THE STANDARD (?) TOOL Source 1 st gen. G th gen. (G+1) th gen. M th gen. N 0 particles Convergence to the fundamental mode ϕ 1 (statistical equilibrium) Stationarity: sample ϕ 1 = <ϕ 1 (g)> Hypothesis: (I)ID replicas What about correlations? CEA March 22nd 2016 PAGE 6
7 A TOY MODEL OF A NUCLEAR REACTOR Neutrons in a box Scattering Capture Fission Descendants per fission Reflecting boundary conditions Assumption: the reactor is critical Expected fundamental mode ϕ 1 : spatially uniform over the box CEA March 22nd 2016 PAGE 7
8 IMPACT OF SYSTEM SIZE L ON POWER ITERATION Generations Delta-like source at the center of the box Initial number of neutrons per generation N = 10 4 CEA March 22nd 2016 PAGE 8
9 IMPACT OF SYSTEM SIZE L ON POWER ITERATION Neutrons per generation N = 10 4 Neutron clustering CEA March 22nd 2016 PAGE 9
10 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Pure diffusion (ideal gas) Initial condition: N 0 particles with uniform density CEA March 22nd 2016 PAGE 10
11 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Fluctuations: Initial condition: N 0 particles with uniform density CEA March 22nd 2016 PAGE 11
12 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Fluctuations: Initial condition: N 0 particles with uniform density CEA March 22nd 2016 PAGE 12
13 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Diffusion + branching + capture (critical gas) Initial condition: N 0 particles with uniform density CEA March 22nd 2016 PAGE 13
14 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Fluctuations: Initial condition: N 0 particles with uniform density CEA March 22nd 2016 PAGE 14
15 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Mixing time Initial condition: N 0 particles with uniform density Clustering Capture Fission Diffusion CEA March 22nd 2016 PAGE 15
16 SPATIAL BEHAVIOUR OF THE NEUTRON DENSITY Mixing time Renewal time? Initial condition: N 0 particles with uniform density Clustering Capture Fission Diffusion CEA March 22nd 2016 PAGE 16
17 IMPACT OF POPULATION SIZE N ON POWER ITERATION Generations Delta-like source at the center of the box System size L = 400 cm CEA March 22nd 2016 PAGE 17
18 IMPACT OF POPULATION SIZE N ON POWER ITERATION N System size L = 400 cm Neutron clustering CEA March 22nd 2016 PAGE 18
19 THE ENTROPY FUNCTION: CONVERGENCE ANALYSIS Shannon entropy: m m Generations to convergence: CEA March 22nd 2016 PAGE 19
20 THE EFFECTS OF CLUSTERING ON THE ENTROPY FUNCTION Shannon entropy: Theoretical expected value for independent replicas Measured value Impact of correlations between generations CEA March 22nd 2016 PAGE 20
21 ANALYSIS OF SPATIAL MOMENTS: THE CENTER OF MASS CEA March 22nd 2016 PAGE 21
22 A STATISTICAL MECHANICS DESCRIPTION Neutrons as a collection of N stochastic particles: {x 1, x 2, x i, x N } A remarkable identity for the spatial moments: Square COM Mean square displacement: Mean square pair distance: CEA March 22nd 2016 PAGE 22
23 A STATISTICAL MECHANICS DESCRIPTION Neutrons as a collection of N stochastic particles: {x 1, x 2, x i, x N } A remarkable identity for the spatial moments: Average particle density ψ Square COM Mean square displacement: Pair correlation function h Mean square pair distance: CEA March 22nd 2016 PAGE 23
24 RECIPROCITY OF RANDOM WALKS Forward time flow Backward time flow Measure in z z t Source Measure in z z t Source CEA March 22nd 2016 PAGE 24
25 THE AVERAGE NEUTRON DENSITY z Measurement z t Source z 0 CEA March 22nd 2016 PAGE 25
26 THE PAIR CORRELATION FUNCTION Correlated measurements z 1 z 2 z 1 à z z 2 à z z à z 0 z t Source z 0 CEA March 22nd 2016 PAGE 26
27 THE HOMOGENEOUS CUBE REACTOR Average neutron density: Pair correlation function: System size L Single dimensionless parameter Population size N Migration area M 2 CEA March 22nd 2016 PAGE 27
28 POWER ITERATION AS A FUNCTION OF χ Uniform initial CEA March 22nd 2016 PAGE 28 condition
29 POWER ITERATION AS A FUNCTION OF χ Uniform initial CEA March 22nd 2016 PAGE 29 condition
30 THE HOMOGENEOUS CUBE REACTOR: SPATIAL MOMENTS Mean square displacement Mean square pair distance CEA March 22nd 2016 PAGE 30
31 THE HOMOGENEOUS CUBE REACTOR: SPATIAL MOMENTS Mean square displacement Mean square pair distance Square COM Fluctuations of COM CEA March 22nd 2016 PAGE 31
32 SPATIAL MOMENTS: STATISTICAL ANALYSIS Theory MC Theory MC CEA March 22nd 2016 PAGE 32
33 CONCLUSIONS q StaGsGcal mechanics approach to power iteragon q Neutron clustering can be suppressed by acgng on χ q Applicability to real- world systems? CEA March 22nd 2016 PAGE 33
34 Thanks for your axengon q E. Dumonteil et al., Annals of Nuclear Energy 63, (2014). q A. Zoia, E. Dumonteil, A. Mazzolo, C. de Mulatier, A. Rosso, Phys. Rev. E 90, (2014). q C. de Mulatier, E. Dumonteil, A. Rosso, A. Zoia, J. Stat. Mech. P08021 (2015). q B. Houchmandzadeh, E. Dumonteil, A. Mazzolo, A. Zoia, Phys. Rev. E 92, (2015). q M. Nowak et al., Monte Carlo power iteration: entropy and spatial correlations, submitted. CEA March 22nd 2016 PAGE 34
35 PAGE 35 CEA 10 AVRIL 2012 APRILE 13, 2016 Commissariat à l énergie atomique et aux énergies alternagves Centre de Saclay Gif- sur- YveXe Cedex T. +33 (0) Secr :+33 (0) Etablissement public à caractère industriel et commercial RCS Paris B DEN/DANS DM2S SERMA
MONTE CARLO POWER ITERATION: ENTROPY AND SPATIAL CORRELATIONS
MONTE CARLO POWER ITERATION: ENTROPY AND SPATIAL CORRELATIONS ANDREA ZOIA, M. NOWAK (CEA/SACLAY) E. DUMONTEIL, A. ONILLON (IRSN) J. MIAO, B. FORGET, K. S. SMITH (MIT) NEA EGAMCT meeting Andrea ZOIA DEN/DANS/DM2S/SERMA/LTSD
More informationMechanical modelling of SiC/SiC composites and design criteria
Mechanical modelling of SiC/SiC composites and design criteria F. Bernachy CEA, DEN/DMN/SRMA/LC2M, Gif-sur-Yvette, France L. Gélébart CEA, DEN/DMN/SRMA/LC2M, Gif-sur-Yvette, France J. Crépin Centre des
More informationQUALIFICATION OF A CFD CODE FOR REACTOR APPLICATIONS
QUALIFICATION OF A CFD CODE FOR REACTOR APPLICATIONS Ulrich BIEDER whole TrioCFD Team DEN-STMF, CEA, UNIVERSITÉ PARIS-SACLAY www.cea.fr SÉMINAIRE ARISTOTE, NOVEMBER 8, 2016 PAGE 1 Outline Obective: analysis
More informationQuality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge
Quality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge Hamid MAKIL (CEADRT/LIST/LCAE) Patrick BRISSET (IAEA) ICARST 2017, 24 28 April
More informationModelling of Specimen Interaction with Ferrite Cored Coils by Coupling Semi-Analytical and Numerical Techniques
Modelling of Specimen Interaction with Ferrite Cored Coils by Coupling Semi-Analytical and Numerical Techniques A. Skarlatos, E. Demaldent, A. Vigneron and C. Reboud 25 th 28 th of June, Bratislava, Slovak
More informationInvestigation of Prompt Fission Neutron and Gamma Spectra with their covariance matrices. Application to 239 Pu+n th, 238 U+n 1.
Investigation of Prompt Fission Neutron and Gamma Spectra with their covariance matrices. Application to 239 Pu+n th, 238 U+n 1.8MeV, 235 U+n th O. Litaize, L. Berge, D. Regnier, O. Serot, Y. Peneliau,
More informationMAGNETIC ANISOTROPY IN TIGHT-BINDING
MAGNETIC ANISOTROPY IN TIGHT-BINDING Cyrille Barreteau Magnetic Tight-Binding Workshop, London10-11 Sept. 2012 9 SEPTEMBRE 2012 CEA 10 AVRIL 2012 PAGE 1 SOMMAIRE TB Model TB 0 : Mehl & Papaconstantopoulos
More informationCode Strategy for Simulating Severe Accident Scenario
Code Strategy for Simulating Severe Accident Scenario C. SUTEAU, F. SERRE, J.-M; RUGGIERI, F. BERTRAND -CEA- March 4-7, 2013, Paris, France christophe.suteau@cea.fr OULINES INTRODUCTION AND CONTEXT REFERENCE
More informationULTRASONIC WAVE PROPAGATION IN DISSIMILAR METAL WELDS APPLICATION OF A RAY-BASED MODEL AND COMPARISON WITH EXPERIMENTAL RESULTS
ULTRASONIC WAVE PROPAGATION IN DISSIMILAR METAL WELDS APPLICATION OF A RAY-BASED MODEL AND COMPARISON WITH EXPERIMENTAL RESULTS Audrey GARDAHAUT 1, Hugues LOURME 1, Frédéric JENSON 1, Shan LIN 2, Masaki
More informationTHERMOHYDRAULIC TRANSIENTS IN BOILING HELIUM NATURAL CIRCULATION LOOPS
THERMOHYDRAULIC TRANSIENTS IN BOILING HELIUM NATURAL CIRCULATION LOOPS Hernán FURCI Director: Chantal MEURIS Supervisor: Bertrand BAUDOUY Laboratoire de Cryogénie et Station d Essais SACM/IRFU/CEA de Saclay
More informationMass transfer kinetics of uranium(vi) and plutonium(iv) extracted by N,Ndialkylamides. Comparison of different techniques
Mass transfer kinetics of uranium(vi) and plutonium(iv) extracted by N,Ndialkylamides Comparison of different techniques R. Berlemont 1, A. Lélias 1, M. Miguirditchian 1, J.-P. Simonin 2 1- CEA Marcoule,
More informationA DFA ON AES BASED ON THE ENTROPY OF ERROR DISTRIBUTIONS
A DFA ON AES BASED ON THE ENTROPY OF ERROR DISTRIBUTIONS FDTC2012 Ronan Lashermes, Guillaume Reymond, Jean-Max Dutertre, Jacques Fournier, Bruno Robisson and Assia Tria 9 SEPTEMBER 2012 INTRODUCTION Introduction
More informationN/réf. AP/cp Votre N/réf. AP/cp: Ecublens, April 30, 2014
INSTITUT DE PHYSIQUE DE L'ENERGIE ET DES PARTICULES (IPEP) Laboratoire de physique des réacteurs et de comportement des systèmes (LRS) Université Paris Sud Centre d Orsay Service des Etudes Doctorales
More informationECT Lecture 2. - Reactor Antineutrino Detection - The Discovery of Neutrinos. Thierry Lasserre (Saclay)
ECT Lecture 2 - Reactor Antineutrino Detection - The Discovery of Neutrinos Thierry Lasserre (Saclay) Reactor Neutrino Detection Inverse Beta Decay p + anti-v e à e + + n cross section @2 MeV : 5 10-43
More information1 Introduction. É É â. EPJ Web of Conferences 42, (2013) C Owned by the authors, published by EDP Sciences, 2013
É É EPJ Web of Conferences 42, 05004 (2013) DOI: 10.1051/ epjconf/ 20134205004 C Owned by the authors, published by EDP Sciences, 2013 Reactivity effect breakdown calculations with deterministic and stochastic
More informationRecent Developments in the TRIPOLI-4 Monte-Carlo Code for Shielding and Radiation Protection Applications
Recent Developments in the TRIPOLI-4 Monte-Carlo Code for Shielding and Radiation Protection Applications Yi-Kang LEE, Fadhel MALOUCH, and the TRIPOLI-4 Team CEA-Saclay France Journées Codes de calcul
More informationPrototypes and fuel cycle options including transmutation
A S T R I D Prototypes and fuel cycle options including transmutation General introduction, GEN IV fast reactors Transmutation demonstration Fuel cycle Conclusions www.cea.fr DEN/CAD/DER/CPA Jean-Paul
More informationSupplementary Information:
Supplementary Information: Atomistic Simulation of Solubilization of Polycyclic Aromatic Hydrocarbons in a Sodium Dodecyl Sulfate Micelle Xujun Liang 1,2,3, Massimo Marchi 2,3, Chuling Guo 1,4, Zhi Dang
More informationPS1-10 COMPARISON OF SIZE-DETERMINING TECHNIQUES FOR NANOPARTICLES IN SUSPENSION: APPLICATION TO Ag NPs.
PS1-10 COMPARISON OF SIZE-DETERMINING TECHNIQUES FOR NANOPARTICLES IN SUSPENSION: APPLICATION TO Ag NPs Sylvie Motellier, Nathalie Pélissier, Jean-Gabriel Mattei, Olivier Sicardy 8 November 2016 Univ.
More informationRecent developments in the TRIPOLI-4 Monte-Carlo code for shielding and radiation protection applications
Recent developments in the TRIPOLI-4 Monte-Carlo code for shielding and radiation protection applications Fadhel Malouch 1,a, Emeric Brun 1, Cheikh Diop 1, François-Xavier Hugot 1, Cédric Jouanne 1, Yi-Kang
More informationNEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES
NEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES PASCAL FICHET, C MOUGEL, Y DESNOYERS, P SARDINI, H WORD DEN SERVICE D ETUDES ANALYTIQUES
More informationNew methods implemented in TRIPOLI-4. New methods implemented in TRIPOLI-4. J. Eduard Hoogenboom Delft University of Technology
New methods implemented in TRIPOLI-4 New methods implemented in TRIPOLI-4 J. Eduard Hoogenboom Delft University of Technology on behalf of Cheikh Diop (WP1.1 leader) and all other contributors to WP1.1
More informationBEAM DYNAMICS STUDIES FOR HILUMI LHC
BEAM DYNAMICS STUDIES FOR HILUMI LHC BARBARA DALENA IN COLLABORATION WITH: J. PAYET, A. CHANCÉ, O. GABOUEV The HiLumi LHC Design Study is included in the High Luminosity LHC project and is partly funded
More informationDiffusion coefficients and critical spectrum methods in Serpent
Diffusion coefficients and critical spectrum methods in Serpent Serpent User Group Meeting 2018 May 30, 2018 Espoo, Finland A. Rintala VTT Technical Research Centre of Finland Ltd Overview Some diffusion
More informationLecture 20 Reactor Theory-V
Objectives In this lecture you will learn the following We will discuss the criticality condition and then introduce the concept of k eff.. We then will introduce the four factor formula and two group
More informationHigh performance computing for neutron diffusion and transport equations
High performance computing for neutron diffusion and transport equations Horizon Maths 2012 Fondation Science Mathématiques de Paris A.-M. Baudron, C. Calvin, J. Dubois, E. Jamelot, J.-J. Lautard, O. Mula-Hernandez
More informationOn the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality Calculations.
Organized and hosted by the Canadian Nuclear Society. Vancouver, BC, Canada. 2006 September 10-14 On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality
More informationStudy of X-ray diagnostics for corium-sodium interaction during severe accident scenario
Study of X-ray diagnostics for corium-sodium interaction during severe accident scenario PHENIICS Fest Orsay, 31 st May, 2017 Shifali SINGH DEN/DTN/SMTA/LPMA CEA, Cadarache Christophe Journeau Thesis Director
More informationESNII + WP7 Fuel Safety
ESNII + WP7 Fuel Safety Nathalie CHAUVIN CEA Cadarache Fuel Studies Department CEA/DEN/Cad ESNII + 24 MARS 2015 17-19 March, 2015 PAGE 1 WP7 Fuel Safety Fuel characteristics of 3 prototypes (starting cores)
More informationImpact of Photon Transport on Power Distribution
Impact of Photon Transport on Power Distribution LIEGEARD Clément, CALLOO Ansar, MARLEAU Guy, GIRARDI Enrico Électricité de France, R&D, Simulation neutronique techniques de l information et calcul scientifique
More informationComparison of Monte Carlo methods for adjoint neutron transport
Eur. Phys. J. Plus (2018) 133: 317 DOI 10.1140/epjp/i2018-12132-9 Regular Article THE EUROPEAN PHYSICAL JOURNAL PLUS Comparison of Monte Carlo methods for adjoint neutron transport Vito Vitali 1, Sandra
More informationDIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR
DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR G. Bignan, J.C. Guyard Commisariat à l Energie Atomique CE CADARACHE DRN/DER/SSAE
More informationGEM TOMOGRAPHIC MEASUREMENTS FOR WEST AND VALIDATION STRATEGIES
GEM TOMOGRAPHIC MEASUREMENTS FOR WEST AND VALIDATION STRATEGIES 2 nd IAEA TM FDPVA 30 May-2 June 2017 Boston (USA) D.Mazon Many thanks to A. Jardin PAGE 1 GENERAL INTRODUCTION The tomographic SXR project
More informationCross Section Generation Strategy for High Conversion Light Water Reactors Bryan Herman and Eugene Shwageraus
Cross Section Generation Strategy for High Conversion Light Water Reactors Bryan Herman and Eugene Shwageraus 1 Department of Nuclear Science and Engineering Massachusetts Institute of Technology 77 Massachusetts
More informationSENSITIVITY ANALYSIS OF ALLEGRO MOX CORE. Bratislava, Iľkovičova 3, Bratislava, Slovakia
SENSITIVITY ANALYSIS OF ALLEGRO MOX CORE Jakub Lüley 1, Ján Haščík 1, Vladimír Slugeň 1, Vladimír Nečas 1 1 Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava,
More informationSolving the neutron slowing down equation
Solving the neutron slowing down equation Bertrand Mercier, Jinghan Peng To cite this version: Bertrand Mercier, Jinghan Peng. Solving the neutron slowing down equation. 2014. HAL Id: hal-01081772
More informationThe Boltzmann Equation and Its Applications
Carlo Cercignani The Boltzmann Equation and Its Applications With 42 Illustrations Springer-Verlag New York Berlin Heidelberg London Paris Tokyo CONTENTS PREFACE vii I. BASIC PRINCIPLES OF THE KINETIC
More informationChapter V: Interactions of neutrons with matter
Chapter V: Interactions of neutrons with matter 1 Content of the chapter Introduction Interaction processes Interaction cross sections Moderation and neutrons path For more details see «Physique des Réacteurs
More information2. The Steady State and the Diffusion Equation
2. The Steady State and the Diffusion Equation The Neutron Field Basic field quantity in reactor physics is the neutron angular flux density distribution: Φ( r r, E, r Ω,t) = v(e)n( r r, E, r Ω,t) -- distribution
More informationNanocomposite for building constructions and civil infrastructures: European network pilot production line to promote industrial application cases.
PROJECT NANOLEAP (646397)- H2020-NMP-PILOTS-2014 NMP1-2014: Open access pilot plants for cost effective nanocomposites Nanocomposite for building constructions and civil infrastructures: European network
More informationSerpent Monte Carlo Neutron Transport Code
Serpent Monte Carlo Neutron Transport Code NEA Expert Group on Advanced Monte Carlo Techniques, Meeting September 17 2012 Jaakko Leppänen / Tuomas Viitanen VTT Technical Research Centre of Finland Outline
More informationPreventing xenon oscillations in Monte Carlo burnup calculations by forcing equilibrium
Preventing xenon oscillations in Monte Carlo burnup calculations by forcing equilibrium Aarno Isotaloa), Jaakko Leppänenb), Jan Dufekcc) a) Aalto University, Finland b) VTT Technical Research Centrte of
More informationTime-Dependent Statistical Mechanics 1. Introduction
Time-Dependent Statistical Mechanics 1. Introduction c Hans C. Andersen Announcements September 24, 2009 Lecture 1 9/22/09 1 Topics of concern in the course We shall be concerned with the time dependent
More informationA Hybrid Stochastic Deterministic Approach for Full Core Neutronics Seyed Rida Housseiny Milany, Guy Marleau
A Hybrid Stochastic Deterministic Approach for Full Core Neutronics Seyed Rida Housseiny Milany, Guy Marleau Institute of Nuclear Engineering, Ecole Polytechnique de Montreal, C.P. 6079 succ Centre-Ville,
More informationMarkov Chain Monte Carlo The Metropolis-Hastings Algorithm
Markov Chain Monte Carlo The Metropolis-Hastings Algorithm Anthony Trubiano April 11th, 2018 1 Introduction Markov Chain Monte Carlo (MCMC) methods are a class of algorithms for sampling from a probability
More informationApplicability of Quasi-Monte Carlo for lattice systems
Applicability of Quasi-Monte Carlo for lattice systems Andreas Ammon 1,2, Tobias Hartung 1,2,Karl Jansen 2, Hernan Leovey 3, Andreas Griewank 3, Michael Müller-Preussker 1 1 Humboldt-University Berlin,
More informationDetermination of the boron content in polyethylene samples using the reactor Orphée
Determination of the boron content in polyethylene samples using the reactor Orphée F. Gunsing, A. Menelle CEA Saclay, F-91191 Gif-sur-Yvette, France O. Aberle European Organization for Nuclear Research
More informationR&D ON FUTURE CIRCULAR COLLIDERS
R&D ON FUTURE CIRCULAR COLLIDERS Double Chooz ALICE Edelweiss HESS Herschel CMS Detecting radiations from the Universe. Conseil Scientifique de l Institut 2015 Antoine Chance and Maria Durante MOTIVATIONS
More informationPrompt Alpha Calculation With Monte Carlo Code JMCT
Prompt Alpha Calculation With Monte Carlo Code JMCT Rui LI 1,2, Tao YE 1, Gang LI 1,2 *, Yun BAI 1, Li DENG 1,2 1 Institute of Applied Physics and Computational Mathematics(IAPCM): FengHao East Road No.2,
More informationSpatio-temporal correlations in fuel pin simulation : prediction of true uncertainties on local neutron flux (preliminary results)
Spatio-temporal correlations in fuel pin simulation : prediction of true uncertainties on local neutron flux (preliminary results) Anthony Onillon Neutronics and Criticality Safety Assessment Department
More informationCore Physics Second Part How We Calculate LWRs
Core Physics Second Part How We Calculate LWRs Dr. E. E. Pilat MIT NSED CANES Center for Advanced Nuclear Energy Systems Method of Attack Important nuclides Course of calc Point calc(pd + N) ϕ dn/dt N
More informationELECTRONIC STRUCTURE CALCULATIONS FOR THE SOLID STATE PHYSICS
FROM RESEARCH TO INDUSTRY 32 ème forum ORAP 10 octobre 2013 Maison de la Simulation, Saclay, France ELECTRONIC STRUCTURE CALCULATIONS FOR THE SOLID STATE PHYSICS APPLICATION ON HPC, BLOCKING POINTS, Marc
More informationPhD Qualifying Exam Nuclear Engineering Program. Part 1 Core Courses
PhD Qualifying Exam Nuclear Engineering Program Part 1 Core Courses 9:00 am 12:00 noon, November 19, 2016 (1) Nuclear Reactor Analysis During the startup of a one-region, homogeneous slab reactor of size
More informationFIFRELIN TRIPOLI-4 coupling for Monte Carlo simulations with a fission model. Application to shielding calculations
FIFRELIN TRIPOLI-4 coupling for Monte Carlo simulations with a fission model. Application to shielding calculations Odile Petit 1,*, Cédric Jouanne 1, Olivier Litaize 2, Olivier Serot 2, Abdelhazize Chebboubi
More informationReactor radiation skyshine calculations with TRIPOLI-4 code for Baikal-1 experiments
DOI: 10.15669/pnst.4.303 Progress in Nuclear Science and Technology Volume 4 (2014) pp. 303-307 ARTICLE Reactor radiation skyshine calculations with code for Baikal-1 experiments Yi-Kang Lee * Commissariat
More informationLecture 7 Problem Set-2
Objectives In this lecture you will learn the following In this lecture we shall practice solving problems. We will solve 5 out of 10 problems in Assignment-2. Background Information Mole Molecular weight
More informationProbing the covariance matrix
Probing the covariance matrix Kenneth M. Hanson Los Alamos National Laboratory (ret.) BIE Users Group Meeting, September 24, 2013 This presentation available at http://kmh-lanl.hansonhub.com/ LA-UR-06-5241
More informationSolving Bateman Equation for Xenon Transient Analysis Using Numerical Methods
Solving Bateman Equation for Xenon Transient Analysis Using Numerical Methods Zechuan Ding Illume Research, 405 Xintianshiji Business Center, 5 Shixia Road, Shenzhen, China Abstract. After a nuclear reactor
More informationNonlinear Iterative Solution of the Neutron Transport Equation
Nonlinear Iterative Solution of the Neutron Transport Equation Emiliano Masiello Commissariat à l Energie Atomique de Saclay /DANS//SERMA/LTSD emiliano.masiello@cea.fr 1/37 Outline - motivations and framework
More informationMonte Caro simulations
Monte Caro simulations Monte Carlo methods - based on random numbers Stanislav Ulam s terminology - his uncle frequented the Casino in Monte Carlo Random (pseudo random) number generator on the computer
More informationAPPLICATION OF PYTHON PROGRAMMING TOOLS FOR CRITICALITY SIMULATION OF NEUTRON TRANSPORT IN NUCLEAR REACTOR WITH SLAB GEOMETRY
J. Sci. & Devel. 2015, Vol. 13, No. 6: 1016-1027 Tạp chí Khoa học và Phát triển 2015, tập 13, số 6: 1016-1027 www.vnua.edu.vn APPLICATION OF PYTHON PROGRAMMING TOOLS FOR CRITICALITY SIMULATION OF NEUTRON
More informationOn the use of SERPENT code for few-group XS generation for Sodium Fast Reactors
On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors Raquel Ochoa Nuclear Engineering Department UPM CONTENTS: 1. Introduction 2. Comparison with ERANOS 3. Parameters required
More informationFuel BurnupCalculations and Uncertainties
Fuel BurnupCalculations and Uncertainties Outline Review lattice physics methods Different approaches to burnup predictions Linkage to fuel safety criteria Sources of uncertainty Survey of available codes
More informationComparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods
Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol., pp.836-841 (011) ARTICLE Comparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods Brian C. KIEDROWSKI * and Forrest
More informationMODELLING OF HTRs WITH MONTE CARLO: FROM A HOMOGENEOUS TO AN EXACT HETEROGENEOUS CORE WITH MICROPARTICLES
MODELLING OF HTRs WITH MONTE CARLO: FROM A HOMOGENEOUS TO AN EXACT HETEROGENEOUS CORE WITH MICROPARTICLES Rita PLUKIENE a,b and Danas RIDIKAS a 1 a) DSM/DAPNIA/SPhN, CEA Saclay, F-91191 Gif-sur-Yvette,
More informationKriging models with Gaussian processes - covariance function estimation and impact of spatial sampling
Kriging models with Gaussian processes - covariance function estimation and impact of spatial sampling François Bachoc former PhD advisor: Josselin Garnier former CEA advisor: Jean-Marc Martinez Department
More informationMonte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW
Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW M. Knebel (Presented by V. Valtavirta) Institute for Neutron Physics and Reactor Technology (INR) Reactor Physics
More informationLesson 6: Diffusion Theory (cf. Transport), Applications
Lesson 6: Diffusion Theory (cf. Transport), Applications Transport Equation Diffusion Theory as Special Case Multi-zone Problems (Passive Media) Self-shielding Effects Diffusion Kernels Typical Values
More informationFission Yield CEA-Cadarache
Fission Yield Activities @ CEA-Cadarache Olivier SEROT CEA-Cadarache DEN/DER/SPRC/LEPh 13108 Saint Paul lez Durance France PAGE 1 Content Fission Yield Measurements on Lohengrin @ Institut Laue Langevin
More informationCHARACTERIZATION OF NANOPARTICLES IN URINE FROM RATS EXPOSED TO TITANIUM DIOXIDE NANOPARTICLES
CHARACTERIZATION OF NANOPARTICLES IN URINE FROM RATS EXPOSED TO TITANIUM DIOXIDE NANOPARTICLES Caroline Marie-Desvergne, Thomas Philippe, Muriel Dubosson, Catherine Campo, Michèle Bouchard, Denis Dième,
More informationA Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis
A Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis A. Aures 1,2, A. Pautz 2, K. Velkov 1, W. Zwermann 1 1 Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh Boltzmannstraße
More informationProcessing of Basic Nuclear Data for Criticality Coefficients Calculations of Fast Homogeneous Systems
Processing of Basic Nuclear Data for Criticality Coefficients Calculations of Fast Homogeneous Systems Jefferson Neves Pereira jeffersonnevespereira@gmail.com Instituto Militar de Engenharia Sergio de
More informationSerco Assurance. Resonance Theory and Transport Theory in WIMSD J L Hutton
Serco Assurance Resonance Theory and Transport Theory in WIMSD J L Hutton 2 March 2004 Outline of Talk Resonance Treatment Outline of problem - pin cell geometry U 238 cross section Simple non-mathematical
More informationIntroduction to Computational Biology Lecture # 14: MCMC - Markov Chain Monte Carlo
Introduction to Computational Biology Lecture # 14: MCMC - Markov Chain Monte Carlo Assaf Weiner Tuesday, March 13, 2007 1 Introduction Today we will return to the motif finding problem, in lecture 10
More informationPerturbation/sensitivity calculations with Serpent
SERPENT workshop Cambridge, 17-19 September 2014 Perturbation/sensitivity calculations with Serpent Manuele Auero, Adrien Bidaud, Pablo Rubiolo LPSC/CNRS Grenoble Calculating the complete β e...coupling
More informationMonte Carlo Methods in High Energy Physics I
Helmholtz International Workshop -- CALC 2009, July 10--20, Dubna Monte Carlo Methods in High Energy Physics CALC2009 - July 20 10, Dubna 2 Contents 3 Introduction Simple definition: A Monte Carlo technique
More informationThe Very-Near-Site at Chooz a New Experimental Hall to Study CEnNS
The Very-Near-Site at Chooz a New Experimental Hall to Study CEnNS T. Lasserre1,2, A. Langenkamper3, C. Nones1, J. Rothe4, R. Strauss4, M. Vivier1, V. Wagner1, A. Zolotarova1 CEA, Centre de Saclay, DRF/Irfu,
More informationThe ENDF-6 file 7 and its possible evolutions with respect to the processing needs
The ENDF-6 file 7 and its possible evolutions with respect to the processing needs Claude Mounier Commissariat à l Énergie Atomique et aux Énergies Alternatives (CEA) CEA-SACLAY DEN/DANS/DM2S/SERMA/LLPR,
More informationLesson 9: Multiplying Media (Reactors)
Lesson 9: Multiplying Media (Reactors) Laboratory for Reactor Physics and Systems Behaviour Multiplication Factors Reactor Equation for a Bare, Homogeneous Reactor Geometrical, Material Buckling Spherical,
More informationLecture 18 Neutron Kinetics Equations
24.505 Lecture 18 Neutron Kinetics Equations Prof. Dean Wang For a nuclear reactor to operate at a constant power level, the rate of neutron production via fission reactions should be exactly balanced
More informationExtremely far from equilibrium: the multiscale dynamics of streamer discharges
Extremely far from equilibrium: the multiscale dynamics of streamer discharges Ute Ebert 1,2 1 Centrum Wiskunde & Informatica Amsterdam 2 Eindhoven University of Technology http://www.cwi.nl/~ebert www.cwi.nl/~ebert
More informationNeutronic Calculations of Ghana Research Reactor-1 LEU Core
Neutronic Calculations of Ghana Research Reactor-1 LEU Core Manowogbor VC*, Odoi HC and Abrefah RG Department of Nuclear Engineering, School of Nuclear Allied Sciences, University of Ghana Commentary Received
More informationDetectors in Nuclear Physics: Monte Carlo Methods. Dr. Andrea Mairani. Lectures I-II
Detectors in Nuclear Physics: Monte Carlo Methods Dr. Andrea Mairani Lectures I-II INTRODUCTION Sampling from a probability distribution Sampling from a probability distribution X λ Sampling from a probability
More informationPART I INTRODUCTION The meaning of probability Basic definitions for frequentist statistics and Bayesian inference Bayesian inference Combinatorics
Table of Preface page xi PART I INTRODUCTION 1 1 The meaning of probability 3 1.1 Classical definition of probability 3 1.2 Statistical definition of probability 9 1.3 Bayesian understanding of probability
More information1. Introductory Examples
1. Introductory Examples We introduce the concept of the deterministic and stochastic simulation methods. Two problems are provided to explain the methods: the percolation problem, providing an example
More informationABSTRACT 1 INTRODUCTION
A NODAL SP 3 APPROACH FOR REACTORS WITH HEXAGONAL FUEL ASSEMBLIES S. Duerigen, U. Grundmann, S. Mittag, B. Merk, S. Kliem Forschungszentrum Dresden-Rossendorf e.v. Institute of Safety Research P.O. Box
More informationHigh precision neutron inelastic cross section measurements
High precision neutron inelastic cross section measurements A. Olacel, C. Borcea, M. Boromiza, A. Negret IFIN-HH, DFN Outline The experimental setup GELINA GAINS Data analysis algorithm. Monte Carlo simulations
More informationFirst-Passage Kinetic Monte Carlo Algorithm for Complex Reaction-Diffusion Systems
First-Passage Kinetic Monte Carlo Algorithm for Complex Reaction-Diffusion Systems Aleksandar Donev 1 Lawrence Postdoctoral Fellow Lawrence Livermore National Laboratory In collaboration with: Vasily V.
More informationIntroduction. Problem Summary. Attila Code-to-Code Comparison Subcritical Spent Nuclear Fuel Canister with Primary Neutron and Gamma Sources
Introduction An example spent nuclear fuel canister calculation was performed with Attila, with results compared to the MCNPX Monte Carlo code. The canister contained representative subcritical neutron
More informationVI. Chain Reaction. Two basic requirements must be filled in order to produce power in a reactor:
VI. Chain Reaction VI.1. Basic of Chain Reaction Two basic requirements must be filled in order to produce power in a reactor: The fission rate should be high. This rate must be continuously maintained.
More informationLE JOURNAL DE PHYSIQUE - LETTRES
Nous We Tome 46? 21 1 er NOVEMBRE 1985 LE JOURNAL DE PHYSIQUE - LETTRES J. Physique Lett. 46 (1985) L-985 - L-989 1 er NOVEMBRE 1985, L-985 Classification Physics Abstracts 64.70P - 05.40-75.40 Diffusion
More informationDemonstration of Full PWR Core Coupled Monte Carlo Neutron Transport and Thermal-Hydraulic Simulations Using Serpent 2/ SUBCHANFLOW
Demonstration of Full PWR Core Coupled Monte Carlo Neutron Transport and Thermal-Hydraulic Simulations Using Serpent 2/ SUBCHANFLOW M. Daeubler Institute for Neutron Physics and Reactor Technology (INR)
More informationDevelopment of a New Process for the Selective Extraction of Uranium from Phosphate Rocks
Development of a New Process for the Selective Extraction of Uranium from Phosphate Rocks URAM 23 27 June 2014 G. Bernier, M. Miguirditchian, V. Pacary, C. Balaguer, M. Bertrand, B. Camès, X. Hérès (Radiochemistry
More informationRandom Walks A&T and F&S 3.1.2
Random Walks A&T 110-123 and F&S 3.1.2 As we explained last time, it is very difficult to sample directly a general probability distribution. - If we sample from another distribution, the overlap will
More informationEnergy Dependence of Neutron Flux
Energy Dependence of Neutron Flux B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Contents We start the discussion of the energy
More informationTRANSMUTATION OF CESIUM-135 WITH FAST REACTORS
TRANSMUTATION OF CESIUM-3 WITH FAST REACTORS Shigeo Ohki and Naoyuki Takaki O-arai Engineering Center Japan Nuclear Cycle Development Institute (JNC) 42, Narita-cho, O-arai-machi, Higashi-Ibaraki-gun,
More informationNeutron background studies for
Neutron background studies for Edelweiss programs Introducing ETNomSiQ working group - Past measurements - Monte Carlo studies - Program of measurements and protections for EDELW II G. Gerbier CEA/Saclay,
More informationNonclassical Particle Transport in Heterogeneous Materials
Nonclassical Particle Transport in Heterogeneous Materials Thomas Camminady, Martin Frank and Edward W. Larsen Center for Computational Engineering Science, RWTH Aachen University, Schinkelstrasse 2, 5262
More informationA Deterministic against Monte-Carlo Depletion Calculation Benchmark for JHR Core Configurations. A. Chambon, P. Vinai, C.
A Deterministic against Monte-Carlo Depletion Calculation Benchmark for JHR Core Configurations A. Chambon, P. Vinai, C. Demazière Chalmers University of Technology, Department of Physics, SE-412 96 Gothenburg,
More informationHomogenization Methods for Full Core Solution of the Pn Transport Equations with 3-D Cross Sections. Andrew Hall October 16, 2015
Homogenization Methods for Full Core Solution of the Pn Transport Equations with 3-D Cross Sections Andrew Hall October 16, 2015 Outline Resource-Renewable Boiling Water Reactor (RBWR) Current Neutron
More information