Spatio-temporal correlations in fuel pin simulation : prediction of true uncertainties on local neutron flux (preliminary results)
|
|
- Willa Sims
- 6 years ago
- Views:
Transcription
1 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 EGAMCT meeting Paris, july 07, 2015
2 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
3 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
4 1 - Introduction : Context Underestimation of statistical uncertainties on local scores by Monte Carlo codes true tally variance can be calculated by performing N repeated Monte Carlo simulations with different random number seeds and calculating the variance of this group of N tally Simulation of a quarter core in infinite medium (z = 20cm) with MORET (R1 case) n src = n AC = Neutron flux map Uncertainties estimated by MORET True uncertainties Underestimation is depending on the simulated system mean free path of neutrons, dimension, reflexion conditions, statistical parameters 1/20
5 1 - Introduction : Monte-Carlo simulation for critical systems Monte Carlo simulation for critical systems Neutron source (position/energy) unknown Probabilistic resolution of neutron transport by the power iteration method - Simulation divided i - Initial neutron source (energy/position), number of neutrons per cycle and number of cycles set by user 1 st part : inactive cycles neutron source convergence 2 nd part : active cycles tallies computation Power iteration processus in a critical system [F. Brown LA-UR ,LANL-2005]. For a simulation with n part : number of neutrons per cycle : number of active cycles Tally results : x = 1 N N x i i=1 N = n part : total number of simulated neutrons (histories) Std dev : S x 2 = S2 N with S x 2 = N i=1 (x i x) 2 N 1 Central limit theorem : If N is high enough, x normaly distributed and S x can be used to create the confidence intervals : intervals at 1σ, 2σ, 3σ intervals at 68,2%, 95,5%, 99,7% Hypothesis: No correlations of histories betwees 2/20
6 1 - Introduction : Monte-Carlo simulation for critical systems Simulation of thermal system : mean free path of neutrons low vs system dimension Spatial and temporal correlations of neutron source distributions betwees Illustration for a simulation of fuel pin in infinite homogeneous medium : «temporal» correlations Clustering effect Spatial correlations 53 Neutron source distribution in a PWR fuel pin (3.8 m infinite medium) during 1000 cycles for et neutrons per cycle Initiale source : point source in (0,0,0) Need to take into account the temporal correlations in the calculation of uncertainties 3/20
7 1 - Introduction : Monte-Carlo simulation for critical systems Without inter-cycle correlations : S x = S x N Propagation of uncertainty y = f(x 1, x 2,.., x n ) With correlations : S x = S x = S x i S x = S x i ρ xi x j S x i,j=1 n part ρ xi x j i,j=1 σ 2 y = n i,j=1 V ij = cov x i, x j y y x i x j V ij x= = ρ xi x j σ xi σ xj Dependence of uncertainties to correlations and distribution of simulated histories between and n part Illustration of the effect of correlations on a gaussian distribution µ = 10 σ = 2 ρ i,i+1 = 0 µ = 10 σ = 2 ρ i,i+1 = 0,995 Random normal sampling (no correlation) Random normal sampling with correlations between each sample 4/20
8 1 - Introduction : Monte-Carlo simulation for critical systems Without inter-cycle correlations : S x = S x N Propagation of uncertainty y = f(x 1, x 2,.., x n ) With correlations : S x = S x = S x i S x = S x i ρ xi x j S x i,j=1 n part ρ xi x j i,j=1 σ 2 y = n i,j=1 V ij = cov x i, x j y y x i x j V ij x= = ρ xi x j σ xi σ xj Dependence of uncertainties to correlations and distribution of simulated histories between and n part Illustration of the effect of correlations on a gaussian distribution µ = 10 σ = 2 ρ i,i+1 = 0 µ = 10 σ = 2 ρ i,i+1 = 0,995 Random normal sampling (no correlation) n = 5000 Random normal sampling with correlations between each sample n = /20
9 1 - Introduction : Monte-Carlo simulation for critical systems Without inter-cycle correlations : S x = S x N Propagation of uncertainty y = f(x 1, x 2,.., x n ) With correlations : S x = S x = S x i S x = S x i ρ xi x j S x i,j=1 n part ρ xi x j i,j=1 σ 2 y = n i,j=1 V ij = cov x i, x j y y x i x j V ij x= = ρ xi x j σ xi σ xj Dependence of uncertainties to correlations and distribution of simulated histories between and n part Illustration of the effect of correlations on a gaussian distribution µ = 10 σ = 2 ρ i,i+1 = 0 µ = 10 σ = 2 ρ i,i+1 = 0,995 Random normal sampling (no correlation) n = Random normal sampling with correlations between each sample n = /20
10 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
11 1 - Intro : Context - 2 Fuel pin model Estimation of true uncertainties on local neutron flux in a multi-cells geometry through the computation of temporal inter-cycles correlation/covariance matrix on local neutron flux Generic calculation : Influence of histories distribution between the number of cycles and the number of neutrons per cycle Model : 1,325 cm UO 2 fuel rod : 3,8 m Infinite medium (reflexion on all surfaces : x-/x+/y-/y+/z-/z+) homogeneous flux along z 380 fuel volumes (L cell = 1 cm) Reflective surfaces Cell 1 Reduction to 20 cells for the analysis of temporal correlations (L cell = 19 cm) H 2 O (without bore) UO 2 ( 235 U : 4.3%) Cell 10 Cell 2 Cell 11 MORET 5.B.2 Simulation 4500 independant simulations with different random seed Uniforme initial neutron source distribution spatialy converged source neutrons/cycle, 2000 cycles limitation of clustering effect Pour all cells c, cycle i, run k : Extraction of neutron flux c i,k Cell 20 5/20
12 1 - Intro : Context - 2 Computation of autocorrelation coefficients : Bravais-Pearson estimator Temporal autocorrelation : Same variable (flux), same cell i, different temporal lags k ρ m i, m+k = cov( i m, m+k i ) = i 2 σ i N k ( i m i )( i m+k i ) m=1 N k m=1 ( m i i ) 2 N k m=1( m+k i i ) 2 ρ i m, i m+k = Autocorrelation in the same cell i for a temporal lag of k. i : mean value of in a cell i N : number of cycles i : cell number m : iterator over the cycles k : temporal lag Notation : ρ i m, i m+k = R i [k] Notation for a simulation with N cycles i 1 i 2 i 3 i i i i i i i i i i i 14 i N Cycle k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 1 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 k = 2 Temporal lag k k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 k = 3 Simulation with N cycles : (N-k) iterations available for a temporal lag of k 6/20
13 1 - Intro : Context - 2 Computation of autocorrelation coefficients : Bravais-Pearson estimator This study : 4500 simulations with 2000 cycles R i [k] = N k 4500 p= N k ( i m,p i )( i m+k,p i ) m=1 N k 4500 p=0 ) 2 ( m,p m=1 p=0 i i ) 2 ( m+k,p m=1 i i m : iterator over cycles p : iterator over simulations inconveniant : fast increase of σ R i [k] with the lag k by comparison with a study with only 1 simulation et cycles (same history number : ) p (N-k) iterations for a lag of k Advantage : allow the construction of cycle to cycle correlation / covariance matrix between the simulations Illustrations of i m, i m+k distributions for different values of ρ i m, i m+k ρ m i, m+k = 0 ρ m i, m+k i ρ m i, m+k = 0,25 ρ m = 0,75 ρ m i i i, m+k i, m+k = 0,5 = 1 i i 7/20
14 Estimated uncertainties (1σ) [%] True uncertainties (1σ) [%] 1 - Intro : Context - 2 Comparison of true and estimated uncertainties on local neutron flux 1 4 set of statistical parameters : identical n part and different 3000 independant simulations with different randoms seeds Computation of uncertainties on local neutron flux : standard deviation of the group True uncertainties along z 1/ decrease not respected temporal correlations Axial uncertainties not constant spatial correlations Uncertainties estimated by MORET quasiconstant along z et 1/ 1 Uncertainties estimated by MORET along z 8/20
15 True_uncertainties /MORET_uncertainties True uncertainties (1σ) [%] 1 - Intro : Context - 2 Comparison of true and estimated uncertainties on local neutron flux 1 4 set of statistical parameters : identical n part and different 3000 independant simulations with different randoms seeds Computation of uncertainties on local neutron flux : standard deviation of the group True uncertainties along z 1/ decrease not respected temporal correlations Axial uncertainties not constant spatial correlations Factor of underestimation [21-73] [16-38] Uncertainties estimated by MORET quasiconstant along z et 1/ Strong underestimation of uncertainties Dependance of the underestimation to the number of used cycles [6-13] [2-5] Ratio of true uncertainties to uncertainties estimated by MORET along z 9/20
16 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
17 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats pour 3 Temporal les matrices correlation de corrélation matrix results temporelle : Cell : n 1 Cellule n 1 (1) Diagonal : ρ i, i = 1 ρ = 0.25 ρ = 0.5 ρ = 0.9 (2) off-diagonal : ρ i, i 1 Cellule 1 (extremity of the fuel pin) (1) Coefficients along the principal diagonal : Correlation of one cycle with itself ρ i, i = 1 (2) Off-diagonal coefficients : Correlation of one cycle with one another ρ i, j 1 10/20
18 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats pour 3 Temporal les matrices correlation de corrélation matrix results temporelle : Cell : n 1 Cellule n 1 (1) Diagonal : ρ i, i = 1 (4) Decrease of correlation with the increase of temporal lag ρ = 0.25 ρ = 0.5 ρ = 0.9 ρ 1200, 1800 ρ 1200, 1500 ρ 1200, 1200 ρ 1900, 1500 ρ 1600, 1200 ρ 1300, 900 (3) Identical correlations (same temporal lag : 400) (2) off-diagonal : ρ i, i 1 Cellule 1 (extremity of the fuel pin) (1) Coefficients along the principal diagonal : Correlation of one cycle with itself ρ i, i = 1 (2) Off-diagonal coefficients : Correlation of one cycle with one another ρ i, j 1 (3) Coefficients along a same descending diagonal : Identical correlations same temporal lag (4) For a give, decrease of correlation when the temporal lag increase 10/20
19 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats pour 3 Temporal les matrices correlation de corrélation matrix results temporelle : Cell : n 1 Cellule n 1 Autocorrelation coefficients converged after i 350 Stabilisation of correlations Cellule 1 (extremity of the fuel pin) (1) Coefficients along the principal diagonal : Correlation of one cycle with itself ρ i, i = 1 (2) Off-diagonal coefficients : Correlation of one cycle with one another ρ i, j 1 (3) Coefficients along a same descending diagonal : Identical correlations same temporal lag (4) For a give, decrease of correlation when the temporal lag increase 10/20
20 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats pour 3 Temporal les matrices correlation de corrélation matrix results temporelle : Cell : n 1 Cellule n Cellule 1 (extremity of the fuel pin) zoom Convergence of autocorrelation coefficients R 1 [k] for different temporal lags k in the cell 1. Cell 1 Cell 10 ~ 350 cycles required to have fully converged autocorrelation coefficients and flux per cycle distribution 400 first cycles excluded of our analysis Convergence of σ i (std dev of flux distributions per cycle) for the first 10 fuel volumes of the rod 11/31
21 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats 3 pour Temporal les matrices correlation de corrélation matrix results temporelle : Cell n 1-10 : Cellule n 1 Cell 1 Cell 2 Cell 3 Autocorrelation coefficients for a temporal lag of 1 : Cell Cell Cell Cell Cell 4 Cell 5 Cell 6 Cell Cell Cell Cell Cell Cell Cell 7 Cell 8 Cell 9 Cell 10 12/31
22 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats 3 pour Temporal les matrices correlation de corrélation matrix results temporelle : Cell n 1-10 : Cellule n 1 Cell 1 Cell 2 Cell 3 Autocorrelation coefficients for a temporal lag of 1 : Cell Cell Cell Cell Cell 4 Cell 5 Cell 6 Cell Cell Cell Cell Cell Cell Cell 7 Cell 8 Cell 9 Cell 10 Identical "structures" : correlated results as coming from the same data set Reduction of intercycles correlations when we get closer the center of the rod Effect of the mirror reflexion at the top & bottom surfaces (spatial effect) : Cycle i : cell 1 : neutrons from C1 i-1 + C2 i-1 cell 2: neutrons from C1 i-1 + C2 i-1 + C3 i-1 cell 3: neutrons from C2 i-1 + C3 i-1 + C4 i-1 13/31
23 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Résultats pour les matrices de corrélation temporelle : Cellule n Autocorrelation & autocovariance fonction results Autocorrelation & autocovariance in fonction of the temporal lag k cov i, j = ρ i j σ i σ j R i [k] = cov( i m, m+k i ) 2 σ i Temporal lag k Temporal lag k Autocorrelation expanded over ~ 700 cycles for the most correlated fuel cells different "order" of curves because σ k i different : σ 1 i, σ 2 i,, σ 10 i = 4.28 %, 3.95 %, 3.65 %, 3.36 %, 3.08 %, 2.84 %, 2.62 %, 2.45 %, 2.32 %, 2.26 % Cell 1 Cell 2 Cell 3 Cell 4 Cell 5 Cell 6 Cell 7 Cell 8 Cell 9 Cell 10 R x < 0, R x < 0, Correlation cut-off (arbitrary limits) 14/20
24 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
25 Number of cycles Number of cycles 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : - Résultats pour les 4 matrices True statistical de corrélation uncertainties temporelle : Cellule n 1 ρ ij & cov i, j Map of uncertainties : uncertainties dependency to n part & Uncertainties taking into account temporal correlations : S x = ρ n ij part i,j=1 S x S 1 S = n + 2 ( i) R part i i=1 Number of neutrons per cycle Cellule 1 (extremity) Number of neutrons per cycle Cellule 10 (center) 15/20
26 Number of cycles Number of cycles 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : - Résultats pour les 4 matrices True statistical de corrélation uncertainties temporelle : Cellule n 1 ρ ij & cov i, j Map of uncertainties : uncertainties dependency to n part & Uncertainties taking into account temporal correlations : S x = n part i,j=1 ρ ij S 1 S = n + part i=1 2 ( i) R i σ < 10% σ < 5% σ < 1 % σ < 10% σ < 5% σ < 1 % S x Number of neutrons per cycle Cellule 1 (extremity) Number of neutrons per cycle Cellule 10 (center) Undersampling bias assumed to be zero for low statistics 15/20
27 Number of cycles Number of cycles 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : - Résultats pour les 4 matrices True statistical de corrélation uncertainties temporelle : Cellule n 1 ρ ij & cov i, j Map of uncertainties : uncertainties dependency to n part & Uncertainties taking into account temporal correlations : S x = n part i,j=1 ρ ij S 1 S = n + part i=1 2 ( i) R i σ < 10% σ < 5% σ < 1 % σ < 10% σ < 5% σ < 1 % S x 35% 10% 31% 9% 16% 7% Cpu-time x100 Cpu-time x100 Cpu-time x100 6% 2% Cpu-time x100 Cpu-time x100 Cpu-time x100 3% 2% Number of neutrons per cycle Cellule 1 (extremity) Number of neutrons per cycle Cellule 10 (center) "iso cpu-time" lines 15/20
28 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : - Résultats pour les 4 matrices True statistical de corrélation uncertainties temporelle : Cellule n 1 ρ ij & cov i, j Influence of the number of active cycles on the true statistical uncertainties σ(w/o cor. ) σ(w/ cor. ) = ρ ij i,j=1 Number of active cycles Ratio between uncertainties computed without and with temporal correlations Increase from a factor 9 (cell 10) to 20 (cell 3) of the uncertainties for an imporante number of cycles Equivalent to a reduction of the number of neutrons per cycle respectively of 80 and 400! Exemple : 2 simulations expected to have identical flux uncertainties in the cell 3 n part = = 1 N = n part = = N = /20
29 Standard deviation Standard deviation 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : - Résultats pour les 4 matrices True statistical de corrélation uncertainties temporelle : Cellule n 1 ρ ij & cov i, j Validation of predicted uncertainties (through correlation matrix) with the one obtained by performing N repeated Monte Carlo simulations with different random number seeds S = S i ρ n i j cycle i,j=1 MORET True uncertainties (gaussian fit of flux distribution of 3000 independant simulations) True uncertainties computed with the correlation matrix Very good agreement between the two methods! 17/20
30 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
31 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : 4 statistical - Résultats pour les matrices 5 de - Spatio-temporal corrélation temporelle correlations : Cellule n 1 ρ ij & cov i, j uncertainties Temporal autocorrelation : Same variable (flux), same cells i, different temporal lags k ρ i m, i m+k = cov( i m, i m+k ) σ 2 = ρ i m, i m+k = R i [k] N k ( i m i )( i m+k i ) m=1 N k m=1 ( m i i ) 2 N k m=1( m+k i i ) 2 Reminder i : mean value of in a cell i N : number of cycles i : cell number m : iterator over the cycles k : temporal lag Notation for a simulation with N cycles Spatio-temporal correlations : Same variable (flux), different cells, different temporal lags k C k i,j C k i,j = cov( i m, m+k j ) = σ i σ j N k ( i m i )( j m+k j ) m=1 N k m=1 ( m i i ) 2 N k m=1( m+k j j ) 2 = Correlation between two spatial bins i and j for a temporal lag of k i : mean value of in a cell i N : number of cycles i : cell number m : iterator over the cycles k : temporal lag Notation for a simulation with N cycles 18/20
32 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : 4 statistical - Résultats pour les matrices 5 de - Spatio-temporal corrélation temporelle correlations : Cellule n 1 ρ ij & cov i, j uncertainties Spatio-temporal correlations for different temporal lag k : 380 cells discretisation is used Spatio-temporal correlations extended over ~350 cycles same than the convergence time fo temporal correlations Correlation of closed cells and anti-correlation of apart cells Small spatial correlations in the center and high on the edge shape in "U" of σ i 19/20
33 Summary: 1. Introduction : - Context - Estimation of statistical uncertainties by Monte Carlo codes 2. Estimation inter-cycles correlations - The fuel pin model - methodology 3. Results for temporal autocorrelation matrix 4. Prediction of true uncertainties 5. Results for spatio-temporal correlation matrix 6. Conclusion and perspectives
34 1 - Intro : Context - 2 Fuel pin model / Pearson coefficient 3 - Results : 4 statistical 5 - spatio-temporal - Résultats pour les matrices de corrélation 6 Conclusion temporelle & Perspectives : Cellule n 1 ρ ij & cov i, j uncertainties correlations Conclusions Computation of temporal & spatial correlation matrix for a fuel pin simulation with MORET «Time» to converged the autocorrelation matrix is higher than the one needed for the convergence of the neutron source : ~ 400 cycles Autocorrelations extended over ~ 700 cycles (cells close to the edges) Possible to predict true uncertainties through a computation of autocorrelation matrix important influence of the distribution of histories between n part & : maximum variation of local uncertainties by a factor 20! validation via a comparison with the «standard method» usually used to compute true uncertainties nevertheless. : Huge cpu time needed to have a precise prediction Perspectives Study still in progress Estimation of uncertainties associated to R i k (also dependent of statistical parameters) domain of validity of the predicted uncertainties : Contribution of σ R k to σ S? predictive ability of S computation through a calcul of correlations during the simulation? Comparison of MORET results with the theoretical 1D correlation fonction computed by A. Zoia and E. Dumonteil Application of this study for the R2 case of the benchmark (in progress) Thanks for your attention! 20/20
Symmetry in Monte Carlo. Dennis Mennerdahl OECD/NEA/NSC/WPNCS/AMCT EG, Paris, 18 September 2014
Symmetry in Monte Carlo Dennis Mennerdahl OECD/NEA/NSC/WPNCS/AMCT EG, Paris, 18 September 2014 OVERVIEW Identical events - Full model results contain everything and more Symmetry to improve convergence?
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 informationMONTE 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 informationK-effective of the World and Other Concerns for Monte Carlo Eigenvalue Calculations
Progress in NULER SIENE and TEHNOLOGY, Vol. 2, pp.738-742 (2011) RTILE K-effective of the World and Other oncerns for Monte arlo Eigenvalue alculations Forrest. ROWN Los lamos National Laboratory, Los
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 informationEvaluation of RAPID for a UNF cask benchmark problem
Evaluation of RAPID for a UNF cask benchmark problem Valerio Mascolino, Alireza Haghighat, and Nathan Roskoff Virginia Tech Nuclear Science and Engineering Laboratory Nuclear Engineering Program, Mechanical
More informationØ Set of mutually exclusive categories. Ø Classify or categorize subject. Ø No meaningful order to categorization.
Statistical Tools in Evaluation HPS 41 Dr. Joe G. Schmalfeldt Types of Scores Continuous Scores scores with a potentially infinite number of values. Discrete Scores scores limited to a specific number
More informationVector spaces. DS-GA 1013 / MATH-GA 2824 Optimization-based Data Analysis.
Vector spaces DS-GA 1013 / MATH-GA 2824 Optimization-based Data Analysis http://www.cims.nyu.edu/~cfgranda/pages/obda_fall17/index.html Carlos Fernandez-Granda Vector space Consists of: A set V A scalar
More informationTheir Statistical Analvsis. With Web-Based Fortran Code. Berg
Markov Chain Monter rlo Simulations and Their Statistical Analvsis With Web-Based Fortran Code Bernd A. Berg Florida State Univeisitfi USA World Scientific NEW JERSEY + LONDON " SINGAPORE " BEIJING " SHANGHAI
More informationCost-accuracy analysis of a variational nodal 2D/1D approach to pin resolved neutron transport
Cost-accuracy analysis of a variational nodal 2D/1D approach to pin resolved neutron transport ZHANG Tengfei 1, WU Hongchun 1, CAO Liangzhi 1, LEWIS Elmer-E. 2, SMITH Micheal-A. 3, and YANG Won-sik 4 1.
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 informationA general assistant tool for the checking results from Monte Carlo simulations
A general assistant tool for the checking results from Monte Carlo simulations Koi, Tatsumi SLAC/SCCS Contents Motivation Precision and Accuracy Central Limit Theorem Testing Method Current Status of Development
More informationBEST ESTIMATE PLUS UNCERTAINTY SAFETY STUDIES AT THE CONCEPTUAL DESIGN PHASE OF THE ASTRID DEMONSTRATOR
BEST ESTIMATE PLUS UNCERTAINTY SAFETY STUDIES AT THE CONCEPTUAL DESIGN PHASE OF THE ASTRID DEMONSTRATOR M. Marquès CEA, DEN, DER F-13108, Saint-Paul-lez-Durance, France Advanced simulation in support to
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 informationLecture: Gaussian Process Regression. STAT 6474 Instructor: Hongxiao Zhu
Lecture: Gaussian Process Regression STAT 6474 Instructor: Hongxiao Zhu Motivation Reference: Marc Deisenroth s tutorial on Robot Learning. 2 Fast Learning for Autonomous Robots with Gaussian Processes
More informationUncertainty quantification and visualization for functional random variables
Uncertainty quantification and visualization for functional random variables MascotNum Workshop 2014 S. Nanty 1,3 C. Helbert 2 A. Marrel 1 N. Pérot 1 C. Prieur 3 1 CEA, DEN/DER/SESI/LSMR, F-13108, Saint-Paul-lez-Durance,
More informationAn application of the GAM-PCA-VAR model to respiratory disease and air pollution data
An application of the GAM-PCA-VAR model to respiratory disease and air pollution data Márton Ispány 1 Faculty of Informatics, University of Debrecen Hungary Joint work with Juliana Bottoni de Souza, Valdério
More informationModern Methods of Data Analysis - WS 07/08
Modern Methods of Data Analysis Lecture V (12.11.07) Contents: Central Limit Theorem Uncertainties: concepts, propagation and properties Central Limit Theorem Consider the sum X of n independent variables,
More informationIMPACT OF THE FISSION YIELD COVARIANCE DATA IN BURN-UP CALCULATIONS
IMPACT OF THE FISSION YIELD COVARIANCE DATA IN BRN-P CALCLATIONS O. Cabellos, D. Piedra, Carlos J. Diez Department of Nuclear Engineering, niversidad Politécnica de Madrid, Spain E-mail: oscar.cabellos@upm.es
More informationANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY Manuele Aufiero, Michael Martin and Massimiliano Fratoni University of California, Berkeley,
More information14 - Gaussian Stochastic Processes
14-1 Gaussian Stochastic Processes S. Lall, Stanford 211.2.24.1 14 - Gaussian Stochastic Processes Linear systems driven by IID noise Evolution of mean and covariance Example: mass-spring system Steady-state
More informationNuclear Data Uncertainty Analysis in Criticality Safety. Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany)
NUDUNA Nuclear Data Uncertainty Analysis in Criticality Safety Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany) Workshop on Nuclear Data and Uncertainty Quantification
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 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 informationØ Set of mutually exclusive categories. Ø Classify or categorize subject. Ø No meaningful order to categorization.
Statistical Tools in Evaluation HPS 41 Fall 213 Dr. Joe G. Schmalfeldt Types of Scores Continuous Scores scores with a potentially infinite number of values. Discrete Scores scores limited to a specific
More informationAssessment of the MCNP-ACAB code system for burnup credit analyses
Assessment of the MCNP-ACAB code system for burnup credit analyses N. García-Herranz, O. Cabellos, J. Sanz UPM - UNED International Workshop on Advances in Applications of Burnup Credit for Spent Fuel
More informationStatus of MORET5 source convergence improvements and benchmark proposal for Monte Carlo depletion calculations
Status of MORET5 source convergence improvements and benchmark proposal for Monte Carlo depletion calculations Y. Richet ; W. Haeck ; J. Miss Criticality analysis department Study, Research, Codes Development
More informationA Study of Covariances within Basic and Extended Kalman Filters
A Study of Covariances within Basic and Extended Kalman Filters David Wheeler Kyle Ingersoll December 2, 2013 Abstract This paper explores the role of covariance in the context of Kalman filters. The underlying
More informationStatistics and Data Analysis
Statistics and Data Analysis The Crash Course Physics 226, Fall 2013 "There are three kinds of lies: lies, damned lies, and statistics. Mark Twain, allegedly after Benjamin Disraeli Statistics and Data
More informationImplementation of the CLUTCH method in the MORET code. Alexis Jinaphanh
Implementation of the CLUTCH method in the MORET code Alexis Jinaphanh Institut de Radioprotection et de sûreté nucléaire (IRSN), PSN-EXP/SNC/LNC BP 17, 92262 Fontenay-aux-Roses, France alexis.jinaphanh@irsn.fr
More informationFactor Analysis of Data Matrices
Factor Analysis of Data Matrices PAUL HORST University of Washington HOLT, RINEHART AND WINSTON, INC. New York Chicago San Francisco Toronto London Contents Preface PART I. Introductory Background 1. The
More informationA Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations
A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations S. Nicolas, A. Noguès, L. Manifacier, L. Chabert TechnicAtome, CS 50497, 13593 Aix-en-Provence Cedex
More informationHypothesis Testing hypothesis testing approach
Hypothesis Testing In this case, we d be trying to form an inference about that neighborhood: Do people there shop more often those people who are members of the larger population To ascertain this, we
More informationUncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent 2
6th International Serpent User Group Meeting Politecnico di Milano, Milan, Italy September 26 th -30 th, 2016 Uncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent
More informationCALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS ABSTRACT
CALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS D J Powney AEA Technology, Nuclear Science, Winfrith Technology Centre, Dorchester, Dorset DT2 8DH United Kingdom
More informationMonte Carlo Simulation. CWR 6536 Stochastic Subsurface Hydrology
Monte Carlo Simulation CWR 6536 Stochastic Subsurface Hydrology Steps in Monte Carlo Simulation Create input sample space with known distribution, e.g. ensemble of all possible combinations of v, D, q,
More informationWhy Correlation Matters in Cost Estimating
Why Correlation Matters in Cost Estimating Stephen A. Book The Aerospace Corporation P.O. Box 92957 Los Angeles, CA 90009-29597 (310) 336-8655 stephen.a.book@aero.org 32nd Annual DoD Cost Analysis Symposium
More informationA.BIDAUD, I. KODELI, V.MASTRANGELO, E.SARTORI
SENSITIVITY TO NUCLEAR DATA AND UNCERTAINTY ANALYSIS: THE EXPERIENCE OF VENUS2 OECD/NEA BENCHMARKS. A.BIDAUD, I. KODELI, V.MASTRANGELO, E.SARTORI IPN Orsay CNAM PARIS OECD/NEA Data Bank, Issy les moulineaux
More informationMinitab Project Report Assignment 3
3.1.1 Simulation of Gaussian White Noise Minitab Project Report Assignment 3 Time Series Plot of zt Function zt 1 0. 0. zt 0-1 0. 0. -0. -0. - -3 1 0 30 0 50 Index 0 70 0 90 0 1 1 1 1 0 marks The series
More informationStatistical signal processing
Statistical signal processing Short overview of the fundamentals Outline Random variables Random processes Stationarity Ergodicity Spectral analysis Random variable and processes Intuition: A random variable
More informationBayesian Estimation of Input Output Tables for Russia
Bayesian Estimation of Input Output Tables for Russia Oleg Lugovoy (EDF, RANE) Andrey Polbin (RANE) Vladimir Potashnikov (RANE) WIOD Conference April 24, 2012 Groningen Outline Motivation Objectives Bayesian
More informationNeutronic simulation of a European Pressurised Reactor. OE Montwedi
Neutronic simulation of a European Pressurised Reactor OE Montwedi 18010210 Dissertation submitted in partial fulfilment of the requirements for the degree Master of Engineering at the Potchefstroom Campus
More informationCombining Regressive and Auto-Regressive Models for Spatial-Temporal Prediction
Combining Regressive and Auto-Regressive Models for Spatial-Temporal Prediction Dragoljub Pokrajac DPOKRAJA@EECS.WSU.EDU Zoran Obradovic ZORAN@EECS.WSU.EDU School of Electrical Engineering and Computer
More informationImproved time integration methods for burnup calculations with Monte Carlo neutronics
Improved time integration methods for burnup calculations with Monte Carlo neutronics Aarno Isotalo 13.4.2010 Burnup calculations Solving time development of reactor core parameters Nuclide inventory,
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 informationAdvanced Experimental Design
Advanced Experimental Design Topic 8 Chapter : Repeated Measures Analysis of Variance Overview Basic idea, different forms of repeated measures Partialling out between subjects effects Simple repeated
More informationChapter 3 - Temporal processes
STK4150 - Intro 1 Chapter 3 - Temporal processes Odd Kolbjørnsen and Geir Storvik January 23 2017 STK4150 - Intro 2 Temporal processes Data collected over time Past, present, future, change Temporal aspect
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 informationSpatial inference. Spatial inference. Accounting for spatial correlation. Multivariate normal distributions
Spatial inference I will start with a simple model, using species diversity data Strong spatial dependence, Î = 0.79 what is the mean diversity? How precise is our estimate? Sampling discussion: The 64
More informationEVALUATION OF PWR AND BWR CALCULATIONAL BENCHMARKS FROM NUREG/CR-6115 USING THE TRANSFX NUCLEAR ANALYSIS SOFTWARE
ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method Nashville, Tennessee April 19 23, 2015, on
More informationMonte Carlo Simulations
Monte Carlo Simulations What are Monte Carlo Simulations and why ones them? Pseudo Random Number generators Creating a realization of a general PDF The Bootstrap approach A real life example: LOFAR simulations
More informationSENSITIVITY ANALYSIS BY THE USE OF A SURROGATE MODEL IN LB-LOCA: LOFT L2-5 WITH CATHARE-2 V2.5 CODE
The 12 th International Topical Meeting on Nuclear Reactor Thermal Hydraulics () Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007. Log Number: XXX SENSITIVITY ANALYSIS
More informationENGRG Introduction to GIS
ENGRG 59910 Introduction to GIS Michael Piasecki October 13, 2017 Lecture 06: Spatial Analysis Outline Today Concepts What is spatial interpolation Why is necessary Sample of interpolation (size and pattern)
More informationIf we want to analyze experimental or simulated data we might encounter the following tasks:
Chapter 1 Introduction If we want to analyze experimental or simulated data we might encounter the following tasks: Characterization of the source of the signal and diagnosis Studying dependencies Prediction
More informationPreliminary statistics
1 Preliminary statistics The solution of a geophysical inverse problem can be obtained by a combination of information from observed data, the theoretical relation between data and earth parameters (models),
More informationLecture Notes 1: Vector spaces
Optimization-based data analysis Fall 2017 Lecture Notes 1: Vector spaces In this chapter we review certain basic concepts of linear algebra, highlighting their application to signal processing. 1 Vector
More informationA Probability Review
A Probability Review Outline: A probability review Shorthand notation: RV stands for random variable EE 527, Detection and Estimation Theory, # 0b 1 A Probability Review Reading: Go over handouts 2 5 in
More informationMultiple Random Variables
Multiple Random Variables This Version: July 30, 2015 Multiple Random Variables 2 Now we consider models with more than one r.v. These are called multivariate models For instance: height and weight An
More informationExpectation. DS GA 1002 Statistical and Mathematical Models. Carlos Fernandez-Granda
Expectation DS GA 1002 Statistical and Mathematical Models http://www.cims.nyu.edu/~cfgranda/pages/dsga1002_fall16 Carlos Fernandez-Granda Aim Describe random variables with a few numbers: mean, variance,
More informationA Note on Auxiliary Particle Filters
A Note on Auxiliary Particle Filters Adam M. Johansen a,, Arnaud Doucet b a Department of Mathematics, University of Bristol, UK b Departments of Statistics & Computer Science, University of British Columbia,
More informationTHE ROLE OF CORRELATIONS IN MONTE CARLO CRITICALITY SIMULATIONS
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 OUTLINE q Power iteragon
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 informationVariance. Standard deviation VAR = = value. Unbiased SD = SD = 10/23/2011. Functional Connectivity Correlation and Regression.
10/3/011 Functional Connectivity Correlation and Regression Variance VAR = Standard deviation Standard deviation SD = Unbiased SD = 1 10/3/011 Standard error Confidence interval SE = CI = = t value for
More informationImproved nuclear data for material damage applications in LWR spectra
Improved nuclear data for material damage applications in LWR spectra Focus on uncertainties, 59 Ni, and stainless steel Petter Helgesson,2 Henrik Sjöstrand Arjan J. Koning 3, Dimitri Rochman 4 Stephan
More informationIntroduction to Regression
Introduction to Regression David E Jones (slides mostly by Chad M Schafer) June 1, 2016 1 / 102 Outline General Concepts of Regression, Bias-Variance Tradeoff Linear Regression Nonparametric Procedures
More informationSome thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation)
Some thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation) Dr Robert W. Mills, NNL Research Fellow for Nuclear Data, UK National Nuclear Laboratory.
More informationAccuracy of flaw localization algorithms: application to structures monitoring using ultrasonic guided waves
Première journée nationale SHM-France Accuracy of flaw localization algorithms: application to structures monitoring using ultrasonic guided waves Alain Le Duff Groupe Signal Image & Instrumentation (GSII),
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 informationBLIND SEPARATION OF TEMPORALLY CORRELATED SOURCES USING A QUASI MAXIMUM LIKELIHOOD APPROACH
BLID SEPARATIO OF TEMPORALLY CORRELATED SOURCES USIG A QUASI MAXIMUM LIKELIHOOD APPROACH Shahram HOSSEII, Christian JUTTE Laboratoire des Images et des Signaux (LIS, Avenue Félix Viallet Grenoble, France.
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 informationAnomaly Density Estimation from Strip Transect Data: Pueblo of Isleta Example
Anomaly Density Estimation from Strip Transect Data: Pueblo of Isleta Example Sean A. McKenna, Sandia National Laboratories Brent Pulsipher, Pacific Northwest National Laboratory May 5 Distribution Statement
More informationDOPPLER COEFFICIENT OF REACTIVITY BENCHMARK CALCULATIONS FOR DIFFERENT ENRICHMENTS OF UO 2
Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) DOPPLER COEFFICIENT OF REACTIVITY BENCHMARK
More informationPractical Statistics
Practical Statistics Lecture 1 (Nov. 9): - Correlation - Hypothesis Testing Lecture 2 (Nov. 16): - Error Estimation - Bayesian Analysis - Rejecting Outliers Lecture 3 (Nov. 18) - Monte Carlo Modeling -
More informationIntroduction. Semivariogram Cloud
Introduction Data: set of n attribute measurements {z(s i ), i = 1,, n}, available at n sample locations {s i, i = 1,, n} Objectives: Slide 1 quantify spatial auto-correlation, or attribute dissimilarity
More informationDescriptive Statistics
Descriptive Statistics DS GA 1002 Probability and Statistics for Data Science http://www.cims.nyu.edu/~cfgranda/pages/dsga1002_fall17 Carlos Fernandez-Granda Descriptive statistics Techniques to visualize
More informationSG39 Meeting May 16-17, Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration
SG39 Meeting May 16-17, 2017 Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration Outline Presentation of the proposed methodology (you've already seen this) Results from
More informationExpectation. DS GA 1002 Probability and Statistics for Data Science. Carlos Fernandez-Granda
Expectation DS GA 1002 Probability and Statistics for Data Science http://www.cims.nyu.edu/~cfgranda/pages/dsga1002_fall17 Carlos Fernandez-Granda Aim Describe random variables with a few numbers: mean,
More information(1) SCK CEN, Boeretang 200, B-2400 Mol, Belgium (2) Belgonucléaire, Av. Arianelaan 4, B-1200 Brussels, Belgium
The REBUS Experimental Programme for Burn-up Credit Peter Baeten (1)*, Pierre D'hondt (1), Leo Sannen (1), Daniel Marloye (2), Benoit Lance (2), Alfred Renard (2), Jacques Basselier (2) (1) SCK CEN, Boeretang
More informationParameter Estimation
Parameter Estimation Tuesday 9 th May, 07 4:30 Consider a system whose response can be modeled by R = M (Θ) where Θ is a vector of m parameters. We take a series of measurements, D (t) where t represents
More informationUnsupervised Learning: Dimensionality Reduction
Unsupervised Learning: Dimensionality Reduction CMPSCI 689 Fall 2015 Sridhar Mahadevan Lecture 3 Outline In this lecture, we set about to solve the problem posed in the previous lecture Given a dataset,
More informationStudy of Predictor-corrector methods. for Monte Carlo Burnup Codes. Dan Kotlyar Dr. Eugene Shwageraus. Supervisor
Serpent International Users Group Meeting Madrid, Spain, September 19-21, 2012 Study of Predictor-corrector methods for Monte Carlo Burnup Codes By Supervisor Dan Kotlyar Dr. Eugene Shwageraus Introduction
More informationStructural Reliability
Structural Reliability Thuong Van DANG May 28, 2018 1 / 41 2 / 41 Introduction to Structural Reliability Concept of Limit State and Reliability Review of Probability Theory First Order Second Moment Method
More informationCorrelation analysis. Contents
Correlation analysis Contents 1 Correlation analysis 2 1.1 Distribution function and independence of random variables.......... 2 1.2 Measures of statistical links between two random variables...........
More informationIntroduction to Probability and Stocastic Processes - Part I
Introduction to Probability and Stocastic Processes - Part I Lecture 2 Henrik Vie Christensen vie@control.auc.dk Department of Control Engineering Institute of Electronic Systems Aalborg University Denmark
More informationCritical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 42, No. 1, p. 101 108 (January 2005) TECHNICAL REPORT Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models Shinya KOSAKA
More informationImplementation of new adjoint-based methods for sensitivity analysis and uncertainty quantication in Serpent
Serpent UGM 2015 Knoxville, 1316 October 2015 Implementation of new adjoint-based methods for sensitivity analysis and uncertainty quantication in Serpent Manuele Auero & Massimiliano Fratoni UC Berkeley
More informationNuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor
Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor García-Herranz Nuria 1,*, Panadero Anne-Laurène 2, Martinez Ana 1, Pelloni
More informationStrain analysis.
Strain analysis ecalais@purdue.edu Plates vs. continuum Gordon and Stein, 1991 Most plates are rigid at the until know we have studied a purely discontinuous approach where plates are
More informationGraphical Object Models for Detection and Tracking
Graphical Object Models for Detection and Tracking (ls@cs.brown.edu) Department of Computer Science Brown University Joined work with: -Ying Zhu, Siemens Corporate Research, Princeton, NJ -DorinComaniciu,
More informationn_tof EAR-1 Simulations Neutron fluence Spatial profile Time-to-energy
n_tof EAR-1 Simulations Neutron fluence Spatial profile Time-to-energy A. Tsinganis (CERN/NTUA), V. Vlachoudis (CERN), C. Guerrero (CERN) and others n_tof Annual Collaboration Meeting Lisbon, December
More informationOverview. DS GA 1002 Probability and Statistics for Data Science. Carlos Fernandez-Granda
Overview DS GA 1002 Probability and Statistics for Data Science http://www.cims.nyu.edu/~cfgranda/pages/dsga1002_fall17 Carlos Fernandez-Granda Probability and statistics Probability: Framework for dealing
More informationWorldwide Open Proficiency Test for X Ray Fluorescence Laboratories PTXRFIAEA13. Determination of Major, Minor and Trace Elements in a Clay Sample
Worldwide Open Proficiency Test for X Ray Fluorescence Laboratories PTXRFIAEA13 Determination of Major, Minor and Trace Elements in a Clay Sample IAEA Laboratories, Seibersdorf November 2017 CONTENTS
More informationMCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure vessel for a Swiss PWR
DOI: 10.15669/pnst.4.481 Progress in Nuclear Science and Technology Volume 4 (2014) pp. 481-485 ARTICLE MCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure
More informationWeighted Least Squares
Weighted Least Squares The standard linear model assumes that Var(ε i ) = σ 2 for i = 1,..., n. As we have seen, however, there are instances where Var(Y X = x i ) = Var(ε i ) = σ2 w i. Here w 1,..., w
More informationCALCULATING UNCERTAINTY ON K-EFFECTIVE WITH MONK10
CALCULATING UNCERTAINTY ON K-EFFECTIVE WITH MONK10 Christopher Baker, Paul N Smith, Robert Mason, Max Shepherd, Simon Richards, Richard Hiles, Ray Perry, Dave Hanlon and Geoff Dobson ANSWERS SOFTWARE SERVICE
More informationReview. DS GA 1002 Statistical and Mathematical Models. Carlos Fernandez-Granda
Review DS GA 1002 Statistical and Mathematical Models http://www.cims.nyu.edu/~cfgranda/pages/dsga1002_fall16 Carlos Fernandez-Granda Probability and statistics Probability: Framework for dealing with
More informationProblem 1: Toolbox (25 pts) For all of the parts of this problem, you are limited to the following sets of tools:
CS 322 Final Exam Friday 18 May 2007 150 minutes Problem 1: Toolbox (25 pts) For all of the parts of this problem, you are limited to the following sets of tools: (A) Runge-Kutta 4/5 Method (B) Condition
More informationModel Assisted Survey Sampling
Carl-Erik Sarndal Jan Wretman Bengt Swensson Model Assisted Survey Sampling Springer Preface v PARTI Principles of Estimation for Finite Populations and Important Sampling Designs CHAPTER 1 Survey Sampling
More informationDr. Allen Back. Sep. 23, 2016
Dr. Allen Back Sep. 23, 2016 Look at All the Data Graphically A Famous Example: The Challenger Tragedy Look at All the Data Graphically A Famous Example: The Challenger Tragedy Type of Data Looked at the
More informationSequential Importance Sampling for Rare Event Estimation with Computer Experiments
Sequential Importance Sampling for Rare Event Estimation with Computer Experiments Brian Williams and Rick Picard LA-UR-12-22467 Statistical Sciences Group, Los Alamos National Laboratory Abstract Importance
More information