CPM-3 BENCHMARKING to the DOE/B&W CRITICAL EXPERIMENTS
|
|
- Nathan Miller
- 5 years ago
- Views:
Transcription
1 CPM-3 BENCHMARKING to the DOE/B&W CRITICAL EXPERIMENTS Kenneth M. Smolinske and Rodney L. Grow Utility Resource Associates Corporation 1901 Research Boulevard, Suite 405 Rockville, Maryland ABSTRACT EPRI-CPM-3 was benchmarked to eight of the DOE/B&W critical experiments described in Urania Gadolinia: Nuclear Model Development and Critical Experiment Benchmark, DOE/ET/ , BAW-1810, April Two types of comparisons were made: K-effective and pin power distribution. Two sets of CPM-3 solutions are presented: 1) CPM-3 in the collision probability matrix (CP) solution is indirectly compared to measurement using MCNP as a bridging calculation; and 2) CPM-3 in the method of characteristics (MOC) solution is directly compared to measurement. 1. INTRODUCTION The EPRI development of CPM-3 1 and the benchmarking of CPM-3 are described in a separate paper for this ANS meeting. This paper describes the extensive effort spent in benchmarking CPM-3 to the DOE/B&W critical experiments 2 and the results obtained from this effort. 2. BENCHMARK PROCESS The eight experiments that were selected to be modeled are: Core ID Short Description Results for benchmark Single enrichment cores I 2.46 w/o fuel with water holes only core k-effective and center assembly power distribution II 2.46 w/o fuel with 16 Ag-In-Cd core k-effective V 2.46 w/o fuel and 28 Gd pins (4 w/o Gd/1.94 w/o U235) core k-effective and center assembly power distribution VI 2.46 w/o fuel and 28 Gd pins with 16 Ag-In-Cd rods core k-effective Dual enrichment cores XII 4.02 in 31x31 inner zone and 2.46 w/o in the outer zone core k-effective and center assembly power distribution XIII 4.02 in 31x31 inner zone with 16 B4C rods and core k-effective 2.46 w/o in the outer zone XIV 4.02 and 28 Gd in 31x31 inner zone and 2.46 w/o in the outer zone core k-effective and center assembly power distribution XV 4.02 and 28 Gd in 31x31 inner zone with 16 B4C rods and 2.46 w/o in the outer zone core k-effective 1
2 These cases were selected to test the capability of EPRI-CPM-3 for a variety of enrichment and absorber combinations. Description of the Experiment The benchmark cases are based on a 3x3 array of 15x15 PWR lattices surrounded by a blanket of pins. This core is submerged in borated water in a 5-foot (ID) aluminum tank. The core contains a total of 4961 pins. The horizontal pin layout of the eight cores are shown in Figures 1 through 8. These figures show the southeast quadrant of the core. The boron concentrations listed in the DOE report are in units of gb NAT /10 6 cc of moderator. These values were converted to true ppm. The largest difference was 3 ppm in core 12. General Modeling Considerations The experimental configurations described in the DOE/B&W report are best modeled in three dimensions for the k-effective comparisons and in two dimensions for the pin power distribution comparisons. EPRI-CPM-3 is a two dimensional, multi-group code, so direct comparisons of predicted k-effective to experiment are not possible. In addition, the full two-dimensional layout in EPRI-CPM-3 is too large for most computers to calculate when CPM-3 is run using the collision probability matrix (CP) solution. So, in order to permit indirect comparisons, MCNP was used as a bridge to check the CP solution of CPM-3 for both reactivity and power distribution comparisons. For the method of characteristics (MOC) solution of CPM-3, the full horizontal layout was modeled and the pin power distribution was compared directly to measurement. The k-effective comparisons required that the CPM-3 include a calculated buckling to account for vertical leakage. Benchmark Cases using the Collision Probability Matrix (CP) Solution The CP solution of EPRI-CPM-3 must be compared as a single assembly to a comparable MCNP because CP solution currently cannot solve a problem as large as the actual experiment. The eight single assembly cases model the center 15x15 assembly of the full critical experiment using both EPRI-CPM-3 and MCNP. The center water hole was modeled without the detector, because the detector was inserted only for the pin power experiments. MCNP Cases Used as a Bridge to the Collision Probability Matrix (CP) Solution For comparison to pin power distribution measurement, the full critical experiments are modeled using horizontally explicit two dimensional MCNP cases for the four cores having pin power measurements. These two dimensional MCNP cases include an approximate model of the central detector, because the detector was included when the cores were burned to produce the power distributions. Only the four cores without Ag-In-Cd (silver, indium, cadmium control rods) or B4C rods have pin power distribution measurements. For comparison to measured reactivity, the two dimensional MCNP cases were changed to three dimensional cases with the active core region 150 cm high with a large volume of water below the core and vacuum above the core. All neutrons reaching the boundary of the problem were 2
3 lost. The center water hole was modeled without the detector, because the detector was inserted only for the pin power experiments. Benchmark Cases using the Method of Characteristics (MOC) Solution The full critical experiments are modeled using horizontally explicit CPM-3 cases for the fuel pin cells in the center of the core. The water outside the core was modeled as lumped blocks to simplify the model setup. For comparison to pin power distribution measurement, these CPM-3 cases include an approximate model of the central detector, because the detector was included when the cores were burned to produce the power distributions. Only the four cores without Ag-In-Cd (silver, indium, cadmium control rods) or B4C rods have pin power distribution measurements. For comparison to measured reactivity, the MOC CPM-3 cases have a central water hole and include a calculated axial buckling term. 3. BENCHMARK RESULTS The results of the comparisons are presented in this paper. Table 1 presents the reactivity comparisons for the CPM-3 CP solution. This table shows: 1. the comparisons between each individual core measurement and its corresponding MCNP three dimensional calculation, and 2. the comparisons between the MCNP and EPRI-CPM-3 assembly calculations. The line labeled 3D core shows the K-effective calculated by MCNP for the experiment and the ρ between the MCNP case and the measurement (assumed to be k=1). ρ = (1-k MCNP ) k MCNP. The line labeled Assembly shows the K-infinite calculated by MCNP and CPM-3 using the CP solution for an assembly representing the central 15x15 array of pins in the experiment. This line also shows the ρ between the MCNP case and CPM-3 case. ρ = (k MCNP -k CPM3 ) (k MCNP.* k CPM3 ). The Average Values sub-table shows the average ρ for the 3D core and Assembly cases. The Assembly results are shown both with and without the AgInCd control rods because the CPM-3 modeling of these control rods is still being investigated. Table 2 presents the reactivity comparisons for the CPM-3 MOC solution. This table shows: 1. the comparisons between each individual core measurement and its corresponding CPM-3 calculation with a calculated buckling. 3
4 The main part of the table shows the K-effective calculated by MCNP and by the MOC CPM-3 for the experiment. It also shows three ρ values: 1. between the MCNP case and the measurement (assumed to be k=1), ρ = (1-k MCNP ) k MCNP ; 2. between the CPM-3 case and the measurement (assumed to be k=1), ρ = (1-k CPM3 ) k CPM3 ; and 3. between the MCNP and CPM-3 cases, ρ = (k MCNP -k CPM3 ) (k MCNP.* k CPM3 ). The Average Values sub-table shows the average ρ for the various cases listed above. The comparisons to CPM-3 are shown both with and without the AgInCd control rods because the CPM-3 modeling of these control rods is still being investigated. Figures 9 through 16 show the pin power distributions for the central 15x15 array of pins and are arranged in pairs (three pages per pair) as follows: The figure labeled MCNP vs. Measurement for CORE nn, Using 2D MCNP shows the comparison of MCNP pin power distribution from the two dimensional case vs. the measured pin power distribution. These pin distributions are normalized to for the full assembly (i.e., the full 15x15 array of pins) so the MCNP Avg and the Meas Avg are not exactly because only an eighth of an assembly is presented. The figure labeled MCNP vs. CPM-3 for CORE nn, Using Single Assembly MCNP shows the comparison of MCNP pin power distribution from the single assembly case vs. the CP CPM-3 single assembly pin power distribution. These pin distributions are normalized to for the full assembly (i.e., the full 15x15 array of pins) so the MCNP Avg and the CPM3 Avg are not exactly because only an eighth of an assembly is presented. The figure labeled CPM-3 vs. Measurement for CORE nn, Using MOC CPM-3 shows the comparison of CPM-3 pin power distribution from the MOC case vs. the measured pin power distribution. These pin distributions are normalized to for the full assembly (i.e., the full 15x15 array of pins) so the MCNP Avg and the Meas Avg are not exactly because only an eighth of an assembly is presented. Benchmark Cases using the Collision Probability Matrix (CP) Solution The most significant observations are: The MCNP vs. measurement comparisons have an average bias of about 260 pcm (MCNP is lower than measurement). The MCNP vs. EPRI-CPM-3 single assembly cases (excluding the Ag-In-Cd control rod cases) have an average bias of about 420 pcm (MCNP is lower than EPRI-CPM-3). These comparisons give an inferred measurement bias for EPRI-CPM-3 of about 160 pcm. The MCNP vs. EPRI-CPM-3 cases for the Ag-In-Cd control rods require more investigation. The MCNP vs. measurement power distributions all have a standard distribution of about 1.4%. 4
5 The MCNP vs. EPRI-CPM-3 single assembly power distributions (excluding the Ag-In-Cd control rod cases) all have a standard distribution of about 0.5%. The MCNP vs. EPRI-CPM-3 single assembly power distributions for the Ag-In-Cd control rod cases have standard distributions of about 1.3%. Benchmark Cases using the Method of Characteristics (MOC) Solution The most significant observations are: The CPM-3 vs. measurement comparisons have an average bias of about 190 pcm. On average, CPM-3 is lower than measurement. The CPM-3 vs. measurement power distributions have standard deviations of 1.2% and 1.4% for fuel without Gd. The CPM-3 vs. measurement power distributions for fuel with Gd are 3.4% and 3.9%. The MOC solutions CPM-3 cases are still being investigated. CONCLUSIONS CPM-3 has been benchmarked to a variety of the critical experiment configurations. These results show good agreement for the central assembly pin power distributions and reactivity. Additional work in progress is an attempt to run the full two dimensional experiments using EPRI-CPM-3 and the full three dimensional experiment using a CPM-3/CORETRAN model. The results from these cases and comparisons to measurement will be provided at the May 7-11, 2000 meeting. ACKNOWLEDGEMENTS The results presented in this paper are a subset of the total benchmarking effort of the CPM-3 benchmarking team. This team led by the authors, consisted of the following individuals and organizations identified below. In addition, the CPM-3 development team consisted of EPRI, the utility sponsors, Utility Resource Associates, TransWare Enterprises and Mark Williams. Steven Baker Public Service Electric & Gas TransWare Enterprises Ronald Furia GPU Nuclear Corp. Keith Dehnbostel Northern States Power Co. David Trace and James Miller Virginia Power Juan Luis Francois Instituto de Investigaciones Electricas Mark Williams Independent Consultant Louisiana State University 5
6 REFERENCES 1 CPM-3 Computer Code Manual, FPR-CPM-001-M-001, Volumes 1 5, July Urania Gadolinia: Nuclear Model Development and Critical Experiment Benchmark, DOE/ET/ , BAW-1810, April
7 The pins that are delineated by the bold line in the figure above represent the center assembly for the power distribution comparisons. Figure 1 Core I Pin Layout 7
8 Figure 2 Core II Pin Layout 8
9 The pins that are delineated by the bold line in the figure above represent the center assembly for the power distribution comparisons. Figure 3 Core V Pin Layout 9
10 Figure 4 Core VI Pin Layout 10
11 The pins that are delineated by the bold line in the figure above represent the center assembly for the power distribution comparisons. Figure 5 Core XII Pin Layout 11
12 Figure 6 Core XIII Pin Layout 12
13 The pins that are delineated by the bold line in the figure above represent the center assembly for the power distribution comparisons. Figure 7 Core XIV Pin Layout 13
14 Figure 8 Core XV Pin Layout 14
15 CORE 1 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 2 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 5 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 6 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 12 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 13 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 14 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± CORE 15 Problem MCNP CPM3 ρ 3D core ± vs. meas = 1: mcnp vs cpm3 Assembly ± Table 1 (1 of 2) Collision Probability Matrix (CP) Reactivity Results 15
16 Average Values ρ 3D core ± MCNP vs measurement (k=1) Assembly ± MCNP vs CPM-3 (all) Assembly ± MCNP vs CPM-3 (no AgInCd) Short Description of Cores: CORE 1: 2.46 w/o fuel with water holes only CORE 2: 2.46 w/o fuel with 16 Ag-In-Cd CORE 5: 2.46 w/o fuel and 28 Gd pins (4 w/o Gd/1.94 w/o U235), with four Gd pins on x- and y-axes CORE 6: 2.46 w/o fuel and 28 Gd pins (matches Core 5) with 16 Ag-In-Cd rods CORE 12: Two enrichments: 4.02 in 31x31 inner zone and 2.46 w/o in the outer zone CORE 13: Two enrichments: 4.02 in 31x31 inner zone and 2.46 w/o in the outer zone with 16 B4C rods CORE 14: Two enrichments: 4.02 and 28 Gd in 31x31 inner zone and 2.46 w/o in the outer zone CORE 15: Two enrichments: 4.02 and 28 Gd in 31x31 inner zone and 2.46 w/o in the outer zone with 16 B4C rods Table 1 (2 of 2) Collision Probability Matrix (CP) Reactivity Results 16
17 Case ID ρ CORE 1 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 2 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 5 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 6 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 12 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 13 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 14 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± CORE 15 MCNP MOC CPM3 mcnp vs meas cpm3 vs meas mcnp vs cpm ± Averages ρ ± MCNP vs measurement (k=1) ± CPM-3 vs measurement (k=1) - all ± CPM-3 vs measurement (k=1) - no AgInCd ± MCNP vs CPM-3 (all) ± MCNP vs CPM-3 (no AgInCd) Short Description of Cores: CORE 1: 2.46 w/o fuel with water holes only CORE 2: 2.46 w/o fuel with 16 Ag-In-Cd CORE 5: 2.46 w/o fuel and 28 Gd pins (4 w/o Gd/1.94 w/o U235), with four Gd pins on x- and y-axes CORE 6: 2.46 w/o fuel and 28 Gd pins (matches Core 5) with 16 Ag-In-Cd rods CORE 12: Two enrichments: 4.02 in 31x31 inner zone and 2.46 w/o in the outer zone CORE 13: Two enrichments: 4.02 in 31x31 inner zone and 2.46 w/o in the outer zone with 16 B4C rods CORE 14: Two enrichments: 4.02 and 28 Gd in 31x31 inner zone and 2.46 w/o in the outer zone CORE 15: Two enrichments: 4.02 and 28 Gd in 31x31 inner zone and 2.46 w/o in the outer zone with 16 B4C rods Table 2 Method of Characteristics (MOC) Reactivity Results 17
18 MCNP vs. Measurement for CORE I Using 2D MCNP Detector Water Hole Water Hole Water Hole MCNP (full assembly) Measured MCNP-Measured MCNP Avg MCNP and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff The MCNP power distribution above is from the 2D case. The average uncertainty for the MCNP along the horizontal axis is: 1.5% The average uncertainty for the MCNP for the rest of the assembly is: 1.1% Figure 9 (1 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core I 18
19 MCNP vs. CPM3 for CORE I Using Single Assembly MCNP Water Hole Water Hole Water Hole Water Hole MCNP (single assy) CPM MCNP-CPM MCNP Avg MCNP values are from a CPM3 Avg full assembly normalization Avg Diff CPM3 values are directly from the Std Dev fission reaction rate distribution edit Min Diff Max Diff The MCNP power distribution above is from the single assembly case. The average uncertainty for the MCNP along the horizontal axis is: 0.4% The average uncertainty for the MCNP for the rest of the assembly is: 0.3% Figure 9 (2 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core I 19
20 CPM-3 vs. Measurement for CORE I Using MOC CPM Detector Water Hole Water Hole Water Hole CPM Measured CPM3-Measured CPM3 Avg CPM3 and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff Figure 10 Method of Characteristics (MOC) Pin Power Distribution Reactivity Results for Core I 20
21 MCNP vs. Measurement for CORE V Using 2D MCNP Detector Water Hole Water Hole Gd Pin Water Hole MCNP (full assembly) Measured MCNP-Measured MCNP Avg MCNP and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff The MCNP power distribution above is from the 2D case. The average uncertainty for the MCNP along the horizontal axis is: 1.8% The average uncertainty for the MCNP for the rest of the assembly is: 1.3% Figure 11 (1 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core V 21
22 MCNP vs. CPM3 for CORE V Using Single Assembly MCNP Water Hole Water Hole Water Hole Gd Pin Water Hole MCNP (single assy) CPM MCNP-CPM MCNP Avg MCNP values are from a CPM3 Avg full assembly normalization Avg Diff CPM3 values are directly from the Std Dev fission reaction rate distribution edit Min Diff Max Diff The MCNP power distribution above is from the single assembly case. The average uncertainty for the MCNP along the horizontal axis is: 0.4% The average uncertainty for the MCNP for the rest of the assembly is: 0.3% Figure 11 (2 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core V 22
23 CPM-3 vs. Measurement for CORE V Using MOC CPM Detector Water Hole Water Hole Gd Pin Water Hole CPM Measured CPM3-Measured CPM3 Avg CPM3 and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff Figure 12 Method of Characteristics (MOC) Pin Power Distribution Reactivity Results for Core V 23
24 MCNP vs. Measurement for CORE XII Using 2D MCNP Detector Water Hole Water Hole Water Hole MCNP (full assembly) Measured MCNP-Measured MCNP Avg MCNP and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff The MCNP power distribution above is from the 2D case. The average uncertainty for the MCNP along the horizontal axis is: 1.2% The average uncertainty for the MCNP for the rest of the assembly is: 0.9% Figure 13 (1 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core XII 24
25 MCNP vs. CPM3 for CORE XII Using Single Assembly MCNP Water Hole Water Hole Water Hole Water Hole MCNP (single assy) CPM MCNP-CPM MCNP Avg MCNP values are from a CPM3 Avg full assembly normalization Avg Diff CPM3 values are directly from the Std Dev fission reaction rate distribution edit Min Diff Max Diff The MCNP power distribution above is from the single assembly case. The average uncertainty for the MCNP along the horizontal axis is: 0.5% The average uncertainty for the MCNP for the rest of the assembly is: 0.3% Figure 13 (2 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core XII 25
26 CPM-3 vs. Measurement for CORE XII Using MOC CPM Detector Water Hole Water Hole Water Hole CPM Measured CPM3-Measured CPM3 Avg CPM3 and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff Figure 14 Method of Characteristics (MOC) Pin Power Distribution Reactivity Results for Core XII 26
27 MCNP vs. Measurement for CORE XIV Using 2D MCNP Water Hole Detector Water Hole Water Hole Gd Pin Water Hole MCNP (full assembly) Measured MCNP-Measured MCNP Avg MCNP and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff The MCNP power distribution above is from the 2D case. The average uncertainty for the MCNP along the horizontal axis is: 1.4% The average uncertainty for the MCNP for the rest of the assembly is: 1.0% Figure 15 (1 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core XIV 27
28 MCNP vs. CPM3 for CORE XIV Using Single Assembly MCNP Water Hole Water Hole Water Hole Gd Pin Water Hole MCNP (single assy) CPM MCNP-CPM MCNP Avg MCNP values are from a CPM3 Avg full assembly normalization Avg Diff CPM3 values are directly from the Std Dev fission reaction rate distribution edit Min Diff Max Diff The MCNP power distribution above is from the single assembly case. The average uncertainty for the MCNP along the horizontal axis is: 0.9% The average uncertainty for the MCNP for the rest of the assembly is: 0.6% Figure 15 (2 of 2) Collision Probability Matrix (CP) Pin Power Distribution Reactivity Results for Core XIV 28
29 CPM-3 vs. Measurement for CORE XIV Using MOC CPM Detector Water Hole Water Hole Gd Pin Water Hole CPM Measured CPM3-Measured CPM3 Avg CPM3 and measured values are Meas Avg from full assembly normalizations Avg Diff Std Dev Min Diff Max Diff Figure 16 Method of Characteristics (MOC) Pin Power Distribution Reactivity Results for Core XIV 29
30 30
Application of MCNP Code in Shielding Design for Radioactive Sources
Application of MCNP Code in Shielding Design for Radioactive Sources Ibrahim A. Alrammah Abstract This paper presents three tasks: Task 1 explores: the detected number of as a function of polythene moderator
More informationDRAGON SOLUTIONS FOR BENCHMARK BWR LATTICE CELL PROBLEMS
DRAGON SOLUTIONS FOR BENCHMARK BWR LATTICE CELL PROBLEMS R. Roy and G. Marleau Institut de Génie Nucléaire École Polytechnique de Montréal P.O.Box 6079, Station CV, Montreal, Canada roy@meca.polymtl.ca
More informationSERPENT Cross Section Generation for the RBWR
SERPENT Cross Section Generation for the RBWR Andrew Hall Thomas Downar 9/19/2012 Outline RBWR Motivation and Design Why use Serpent Cross Sections? Modeling the RBWR Generating an Equilibrium Cycle RBWR
More informationBEAVRS benchmark calculations with Serpent-ARES code sequence
BEAVRS benchmark calculations with Serpent-ARES code sequence Jaakko Leppänen rd International Serpent User Group Meeting Berkeley, CA, Nov. 6-8, Outline Goal of the study The ARES nodal diffusion code
More information2-D Reflector Modelling for VENUS-2 MOX Core Benchmark
2-D Reflector Modelling for VENUS-2 MOX Core Benchmark Dušan Ćalić ZEL-EN d.o.o. Vrbina 18 8270, Krsko, Slovenia dusan.calic@zel-en.si ABSTRACT The choice of the reflector model is an important issue in
More informationIMPROVEMENTS TO MONK & MCBEND ENABLING COUPLING & THE USE OF MONK CALCULATED ISOTOPIC COMPOSITIONS IN SHIELDING & CRITICALITY
IMPROVEMENTS TO MONK & MCBEND ENABLING COUPLING & THE USE OF MONK CALCULATED ISOTOPIC COMPOSITIONS IN SHIELDING & CRITICALITY N. Davies, M.J. Armishaw, S.D. Richards and G.P.Dobson Serco Technical Consulting
More informationPSG2 / Serpent a Monte Carlo Reactor Physics Burnup Calculation Code. Jaakko Leppänen
PSG2 / Serpent a Monte Carlo Reactor Physics Burnup Calculation Code Jaakko Leppänen Outline Background History The Serpent code: Neutron tracking Physics and interaction data Burnup calculation Output
More informationInstallation of a Second CLICIT Irradiation Facility at the Oregon State TRIGA Reactor
Installation of a Second CLICIT Irradiation Facility at the Oregon State TRIGA Reactor Robert Schickler and Steve Reese Oregon State University, 100 Radiation Center Corvallis, OR, 97330 USA Corresponding
More informationHELIOS CALCULATIONS FOR UO2 LATTICE BENCHMARKS
M-UR- 98-22. Title: Author@): Submitted to: HELOS CALCULATONS FOR UO2 LATTCE BENCHMARKS R. D. Mosteller nt'l Conf. on Physics of Nuclear Science & Technology slandia, Long sland, NY October 5-8, 1998 Los
More informationVerification of the Hexagonal Ray Tracing Module and the CMFD Acceleration in ntracer
KNS 2017 Autumn Gyeongju Verification of the Hexagonal Ray Tracing Module and the CMFD Acceleration in ntracer October 27, 2017 Seongchan Kim, Changhyun Lim, Young Suk Ban and Han Gyu Joo * Reactor Physics
More informationEvaluation of RAPID for a UNF cask benchmark problem
Evaluation of RAPID for a UNF cask benchmark problem Valerio Mascolino 1,a, Alireza Haghighat 1,b, and Nathan J. Roskoff 1,c 1 Nuclear Science & Engineering Lab (NSEL), Virginia Tech, 900 N Glebe Rd.,
More informationThe Pennsylvania State University. The Graduate School. Department of Mechanical and Nuclear Engineering
The Pennsylvania State University The Graduate School Department of Mechanical and Nuclear Engineering IMPROVED REFLECTOR MODELING FOR LIGHT WATER REACTOR ANALYSIS A Thesis in Nuclear Engineering by David
More informationDaedeok-daero, Yuseong-gu, Daejeon , Republic of Korea b Argonne National Laboratory (ANL)
MC 2-3/TWODANT/DIF3D Analysis for the ZPPR-15 10 B(n, α) Reaction Rate Measurement Min Jae Lee a*, Donny Hartanto a, Sang Ji Kim a, and Changho Lee b a Korea Atomic Energy Research Institute (KAERI) 989-111
More informationTREAT Modeling & Simulation Using PROTEUS
TREAT Modeling & Simulation Using PROTEUS May 24, 2016 ChanghoLee Neutronics Methods and Codes Section Nuclear Engineering Division Argonne National Laboratory Historic TREAT Experiments: Minimum Critical
More informationEvaluation of the Full Core VVER-440 Benchmarks Using the KARATE and MCNP Code Systems
NENE 2015 September 14-17 PORTOROŽ SLOVENIA 24th International Conference Nuclear Energy for New Europe Evaluation of the Full Core VVER-440 Benchmarks Using the KARATE and MCNP Code Systems György Hegyi
More informationClick to edit Master title style
Fun stuff with the built-in response matrix solver 7th International Serpent UGM, Gainesville, FL, Nov. 6 9, 2017 Jaakko Leppänen VTT Technical Research Center of Finland Click to edit Master title Outline
More informationWP1.4: CORE PHYSICS BENCHMARKING OVERVIEW
WP1.4: CORE PHYSICS BENCHMARKING OVERVIEW N.Kolev, N.Petrov, N.Zheleva, G.Todorova, M.Manolova, P.Ivanov, N.Mihaylov (INRNE), J-F.Vidal, F.Damian, P.Bellier, F-X.Hugot (CEA), C.Ahnert, JJ.Herrero, N.Garcia-Herranz,
More informationStatus of the Serpent criticality safety validation package
VTT TECHNICAL RESEARCH CENTRE OF FINLAND LTD Status of the Serpent criticality safety validation package Serpent UGM 2017 Riku Tuominen and Ville Valtavirta, VTT Outline Criticality Safety Evaluation What
More informationSubplane-based Control Rod Decusping Techniques for the 2D/1D Method in MPACT 1. Aaron M. Graham, Benjamin S. Collins, Thomas Downar
Subplane-based Control Rod Decusping Techniques for the 2D/1D Method in MPACT 1 Aaron M. Graham, Benjamin S. Collins, Thomas Downar Department of Nuclear Engineering and Radiological Sciences, University
More informationSPENT FUEL STORAGE RACK REPLACEMENT
DIPDE SPENT FUEL STORAGE RACK REPLACEMENT ISOE Uppsala 2018 Julien BONNEFON (EDF DIPDE) Gérard SACRE (REEL) Christophe COMAS (MILLENNIUM) CONTENTS CONTEXT RADIATION PROTECTION OBJECTIVES MCNP MODELLING
More informationEvaluation of PBMR control rod worth using full three-dimensional deterministic transport methods
Available online at www.sciencedirect.com annals of NUCLEAR ENERGY Annals of Nuclear Energy 35 (28) 5 55 www.elsevier.com/locate/anucene Evaluation of PBMR control rod worth using full three-dimensional
More informationComputing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method
Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol., pp.4-45 (0) ARTICLE Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method Taeshi MITSUYASU,
More informationEXPERIENCE AND EVALUATION OF ADVANCED ON-LINE CORE MONITORING SYSTEM BEACON AT IKATA SITE
EXPERIENCE AND EVALUATION OF ADVANCED ON-LINE CORE MONITORING SYSTEM BEACON AT IKATA SITE Nobumichi Fujitsuka, Hideyuki Tanouchi, Yasuhiro Imamura, Daisuke MizobuchiI IKATA Power Station Shikoku Electric
More informationDEVELOPMENT OF A GRAPHICAL USER INTERFACE FOR IN-CORE FUEL MANAGEMENT USING MCODE
Advances in Nuclear Fuel Management IV (ANFM 2009) Hilton Head Island, South Carolina, USA, April 12-15, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) DEVELOPMENT OF A GRAPHICAL USER
More informationA MULTI-PHYSICS ANALYSIS FOR THE ACTUATION OF THE SSS IN OPAL REACTOR
A MULTI-PHYSICS ANALYSIS FOR THE ACTUATION OF THE SSS IN OPAL REACTOR D. FERRARO Nuclear Engineering Department, INVAP S.E. Esmeralda 356 P.B. C1035ABH, C.A.B.A, Buenos Aires, Argentina P. ALBERTO, E.
More informationA COARSE MESH RADIATION TRANSPORT METHOD FOR PRISMATIC BLOCK THERMAL REACTORS IN TWO DIMENSIONS
A COARSE MESH RADIATION TRANSPORT METHOD FOR PRISMATIC BLOCK THERMAL REACTORS IN TWO DIMENSIONS A Thesis Presented to The Academic Faculty By Kevin John Connolly In Partial Fulfillment Of the Requirements
More informationOECD/NEA EXPERT GROUP ON UNCERTAINTY ANALYSIS FOR CRITICALITY SAFETY ASSESSMENT: CURRENT ACTIVITIES
OECD/NEA EXPERT GROUP ON UNCERTAINTY ANALYSIS FOR CRITICALITY SAFETY ASSESSMENT: CURRENT ACTIVITIES Tatiana Ivanova WPEC Subgroup 33 Meeting Issy-les-Moulineaux May 11, 2011 EG UACSA: Objectives Expert
More informationCORE MONITORING EXPERIENCE WITH GARDEL
CORE MONITORING EXPERIENCE WITH GARDEL Axel Becker, Alejandro Noël Studsvik Scandpower GmbH Studsvik Scandpower Suisse GmbH Abstract The GARDEL core surveillance and analysis system is a standard, modular
More informationGeometric Templates for Improved Tracking Performance in Monte Carlo Codes
Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013) La Cité des Sciences et de l Industrie, Paris, France, October 27-31, 2013 Geometric Templates
More informationMethodology for spatial homogenization in Serpent 2
Methodology for spatial homogenization in erpent 2 Jaakko Leppänen Memo 204/05/26 Background patial homogenization has been one of the main motivations for developing erpent since the beginning of the
More informationModeling Integral Fuel Burnable Absorbers Using the Method of Characteristics
University of Tennessee, Knoxville Trace: Tennessee Research and Creative Exchange Masters Theses Graduate School 12-2014 Modeling Integral Fuel Burnable Absorbers Using the Method of Characteristics Erik
More informationVerification of the 3D Method of characteristics solver in OpenMOC
Verification of the 3D Method of characteristics solver in OpenMOC The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation As Published
More informationReducing 3D MOC Storage Requirements with Axial Onthe-fly
Reducing 3D MOC Storage Requirements with Axial Onthe-fly Ray Tracing The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation As
More informationModeling the ORTEC EX-100 Detector using MCNP
Modeling the ORTEC EX-100 Detector using MCNP MCNP is a general-purpose Monte Carlo radiation transport code for modeling the interaction of radiation with materials based on composition and density. MCNP
More informationBreaking Through the Barriers to GPU Accelerated Monte Carlo Particle Transport
Breaking Through the Barriers to GPU Accelerated Monte Carlo Particle Transport GTC 2018 Jeremy Sweezy Scientist Monte Carlo Methods, Codes and Applications Group 3/28/2018 Operated by Los Alamos National
More informationClick to edit Master title style
Introduction to Serpent Code Fusion neutronics workshop, Cambridge, UK, June 11-12, 2015 Jaakko Leppänen VTT Technical Research Center of Finland Click to edit Master title Outline style Serpent overview
More informationResearch Article Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis
Science and Technology of Nuclear Installations Volume 2, Article ID 68347, 7 pages doi:.55/2/68347 Research Article Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2
More informationChun-Min Su, Ph.D. Center for Measurement Standards, ITRI, Taiwan TCFF Workshop, Da Nang, Vietnam Nov. 12, 2016
Progress in 3-D Pitot Tube and Related Research in Taiwan Chun-Min Su, Ph.D. Center for Measurement Standards, ITRI, Taiwan TCFF Workshop, Da Nang, Vietnam Nov. 12, 2016 Introduction Where on earth are
More informationA premilinary study of the OECD/NEA 3D transport problem using the lattice code DRAGON
A premilinary study of the OECD/NEA 3D transport problem using the lattice code DRAGON Nicolas Martin, Guy Marleau, Alain Hébert Institut de Génie Nucléaire École Polytechnique de Montréal 28 CNS Symposium
More informationState of the art of Monte Carlo technics for reliable activated waste evaluations
State of the art of Monte Carlo technics for reliable activated waste evaluations Matthieu CULIOLI a*, Nicolas CHAPOUTIER a, Samuel BARBIER a, Sylvain JANSKI b a AREVA NP, 10-12 rue Juliette Récamier,
More informationStatus and development of multi-physics capabilities in Serpent 2
Status and development of multi-physics capabilities in Serpent 2 V. Valtavirta VTT Technical Research Centre of Finland ville.valtavirta@vtt.fi 2014 Serpent User Group Meeting Structure Click to of edit
More informationA Method for Estimating Criticality Lower Limit Multiplication Factor. Yoshitaka NAITO NAIS Co., Ltd.
A Method for Estimating Criticality Lower Limit Multiplication Factor Yoshitaka NAITO NAIS Co., Ltd. Progress Grade up of computer performance Sub-criticality becomes to be decided using computed results
More informationClick to edit Master title style
New features in Serpent 2 for fusion neutronics 5th International Serpent UGM, Knoxville, TN, Oct. 13-16, 2015 Jaakko Leppänen VTT Technical Research Center of Finland Click to edit Master title Outline
More informationMURE : MCNP Utility for Reactor Evolution - Description of the methods, first applications and results
MURE : MCNP Utility for Reactor Evolution - Description of the methods, first applications and results O. Méplan, A. Nuttin, O. Laulan, S. David, F. Michel-Sendis, J. Wilson To cite this version: O. Méplan,
More informationA Code for Analyzing Coolant and Offgas Activity in a Light Water Nuclear Reactor: Computer Manual
A Code for Analyzing Coolant and Offgas Activity in a Light Water Nuclear Reactor: Computer Manual A Code for Analyzing Coolant and Offgas WARNING: Please read the Export Control Agreement on the back
More informationRadiological Characterization and Decommissioning of Research and Power Reactors 15602
Radiological Characterization and Decommissioning of Research and Power Reactors 15602 INTRODUCTION Faezeh Abbasi *, Bruno Thomauske *, Rahim Nabbi * RWTH University Aachen The production of the detailed
More informationNeutronics Analysis of TRIGA Mark II Research Reactor. R. Khan, S. Karimzadeh, H. Böck Vienna University of Technology Atominstitute
Neutronics Analysis of TRIGA Mark II Research Reactor R. Khan, S. Karimzadeh, H. Böck Vienna University of Technology Atominstitute 23-03-2010 TRIGA Mark II reactor MCNP radiation transport code MCNP model
More informationVisual Analysis of Lagrangian Particle Data from Combustion Simulations
Visual Analysis of Lagrangian Particle Data from Combustion Simulations Hongfeng Yu Sandia National Laboratories, CA Ultrascale Visualization Workshop, SC11 Nov 13 2011, Seattle, WA Joint work with Jishang
More informationMCNP Monte Carlo & Advanced Reactor Simulations. Forrest Brown. NEAMS Reactor Simulation Workshop ANL, 19 May Title: Author(s): Intended for:
LA-UR- 09-03055 Approved for public release; distribution is unlimited. Title: MCNP Monte Carlo & Advanced Reactor Simulations Author(s): Forrest Brown Intended for: NEAMS Reactor Simulation Workshop ANL,
More information1 st International Serpent User Group Meeting in Dresden, Germany, September 15 16, 2011
1 st International Serpent User Group Meeting in Dresden, Germany, September 15 16, 2011 Discussion notes The first international Serpent user group meeting was held at the Helmholtz Zentrum Dresden Rossendorf
More informationABSTRACT. W. T. Urban', L. A. Crotzerl, K. B. Spinney', L. S. Waters', D. K. Parsons', R. J. Cacciapouti2, and R. E. Alcouffel. 1.
COMPARISON OF' THREE-DIMENSIONAL NEUTRON FLUX CALCULATIONS FOR MAINE YANKEE W. T. Urban', L. A. Crotzerl, K. B. Spinney', L. S. Waters', D. K. Parsons', R. J. Cacciapouti2, and R. E. Alcouffel ABSTRACT
More informationParticle track plotting in Visual MCNP6 Randy Schwarz 1,*
Particle track plotting in Visual MCNP6 Randy Schwarz 1,* 1 Visual Editor Consultants, PO Box 1308, Richland, WA 99352, USA Abstract. A visual interface for MCNP6 has been created to allow the plotting
More informationMultiphysics simulations of nuclear reactors and more
Multiphysics simulations of nuclear reactors and more Gothenburg Region OpenFOAM User Group Meeting Klas Jareteg klasjareteg@chalmersse Division of Nuclear Engineering Department of Applied Physics Chalmers
More informationNUC E 521. Chapter 6: METHOD OF CHARACTERISTICS
NUC E 521 Chapter 6: METHOD OF CHARACTERISTICS K. Ivanov 206 Reber, 865-0040, kni1@psu.edu Introduction o Spatial three-dimensional (3D) and energy dependent modeling of neutron population in a reactor
More informationApplication of the ROSFOND Evaluated Nuclear Data Library for Criticality Calculations in Continuous-Energy Approximation with SCALE-6.
Application of the ROSFOND Evaluated Nuclear Data Library for Criticality Calculations in Continuous-Energy Approximation with SCALE-6.2 E.Rozhikhin, V.Koscheev, A.Yakunin, A.Peregudov Institute of Physics
More informationHIGH PERFORMANCE LARGE EDDY SIMULATION OF TURBULENT FLOWS AROUND PWR MIXING GRIDS
HIGH PERFORMANCE LARGE EDDY SIMULATION OF TURBULENT FLOWS AROUND PWR MIXING GRIDS U. Bieder, C. Calvin, G. Fauchet CEA Saclay, CEA/DEN/DANS/DM2S P. Ledac CS-SI HPCC 2014 - First International Workshop
More informationTABLE OF CONTENTS SECTION 2 BACKGROUND AND LITERATURE REVIEW... 3 SECTION 3 WAVE REFLECTION AND TRANSMISSION IN RODS Introduction...
TABLE OF CONTENTS SECTION 1 INTRODUCTION... 1 1.1 Introduction... 1 1.2 Objectives... 1 1.3 Report organization... 2 SECTION 2 BACKGROUND AND LITERATURE REVIEW... 3 2.1 Introduction... 3 2.2 Wave propagation
More informationA Framework for Systematic Evaluation and Exploration of Design Rules
A Framework for Systematic Evaluation and Exploration of Design Rules Rani S. Ghaida* and Prof. Puneet Gupta EE Dept., University of California, Los Angeles (rani@ee.ucla.edu), (puneet@ee.ucla.edu) Work
More informationCalculation and Verification of Assembly Discontinuity Factors for the DRAGON/PARCS code sequence. Luca Liponi, Julien Taforeau, Alain Hébert
Calculation and Verification of Assembly Discontinuity Factors for the DRAGON/PARCS code sequence Luca Liponi, Julien Taforeau, Alain Hébert École Polytechnique de Montréal, Montréal, QC, Canada Institut
More informationSeismic Soil-Structure Interaction Analysis of the Kealakaha Stream Bridge on Parallel Computers
Seismic Soil-Structure Interaction Analysis of the Kealakaha Stream Bridge on Parallel Computers Seung Ha Lee and Si-Hwan Park Department of Civil and Environmental Engineering University of Hawaii at
More informationCALCULATION OF THE ACTIVITY INVENTORY FOR THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER (MHH) IN PREPARATION FOR DISMANTLING THE FACILITY
CALCULATION OF THE ACTIVITY INVENTORY FOR THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER (MHH) IN PREPARATION FOR DISMANTLING THE FACILITY Gabriele Hampel, Friedemann Scheller, Medical University
More informationDevelopment of a Radiation Shielding Monte Carlo Code: RShieldMC
Development of a Radiation Shielding Monte Carlo Code: RShieldMC Shenshen GAO 1,2, Zhen WU 1,3, Xin WANG 1,2, Rui QIU 1,2, Chunyan LI 1,3, Wei LU 1,2, Junli LI 1,2*, 1.Department of Physics Engineering,
More informationEngineering Effects of Boundary Conditions (Fixtures and Temperatures) J.E. Akin, Rice University, Mechanical Engineering
Engineering Effects of Boundary Conditions (Fixtures and Temperatures) J.E. Akin, Rice University, Mechanical Engineering Here SolidWorks stress simulation tutorials will be re-visited to show how they
More informationOPTIMIZATION OF MONTE CARLO TRANSPORT SIMULATIONS IN STOCHASTIC MEDIA
PHYSOR 2012 Advances in Reactor Physics Linking Research, Industry, and Education Knoxville, Tennessee, USA, April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2010) OPTIMIZATION
More informationIMPLEMENTATION OF SALIVARY GLANDS IN THE BODYBUILDER ANTHROPOMORPHIC PHANTOMS
Computational Medical Physics Working Group Workshop II, Sep 30 Oct 3, 2007 University of Florida (UF), Gainesville, Florida USA on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) IMPLEMENTATION
More informationSpreadsheet and Graphing Exercise Biology 210 Introduction to Research
1 Spreadsheet and Graphing Exercise Biology 210 Introduction to Research There are many good spreadsheet programs for analyzing data. In this class we will use MS Excel. Below are a series of examples
More informationLA-UR- Title: Author(s): Intended for: Approved for public release; distribution is unlimited.
LA-UR- Approved for public release; distribution is unlimited. Title: Author(s): Intended for: Los Alamos National Laboratory, an affirmative action/equal opportunity employer, is operated by the Los Alamos
More informationNeutron Capture Measurements and Resonance Parameters of Gadolinium
NUCLEAR SCIENCE AND ENGINEERING: 180, 86 116 (2015) Neutron Capture Measurements and Resonance Parameters of Gadolinium Y.-R. Kang and M. W. Lee Dongnam Institute of Radiological and Medical Sciences,
More informationGEMINI 8-M Telescopes Project
GEMINI 8-M Telescopes Project TN-O-G0003 Effects on Surface Figure Due to Random Error in Support Actuator Forces for an 8-m Primary Mirror Myung K. Cho Optics Group February 22, 1993 ABSTRACT The effects
More informationGraphical User Interface for Simplified Neutron Transport Calculations
Graphical User Interface for Simplified Neutron Transport Calculations Phase 1 Final Report Instrument No: DE-SC0002321 July 20, 2009, through April 19, 2010 Recipient: Randolph Schwarz, Visual Editor
More informationSulfur-in-Oil Analyzer SLFA-60
Sulfur-in-Oil Analyzer SLFA-60 SLFA-60 for a new generation of petroleum products HORIBA introduces the new standard of transportable sulfur-in-oil analyzers, the SLFA-60. This instrument introduces new
More informationMagnet Alignment Challenges for an MBA Storage Ring*
Magnet Alignment Challenges for an MBA Storage Ring* Animesh Jain Superconducting Magnet Division Brookhaven National Laboratory, Upton, NY 11973, USA 2 nd Workshop on Beam Dynamics Meets Magnets (BeMa2014)
More informationTheoretical Investigations of Tomographic Methods used for Determination of the Integrity of Spent BWR Nuclear Fuel
a UPPSALA UNIVERSITY Department of Radiation Sciences Box 535, S-751 1 Uppsala, Sweden http://www.tsl.uu.se/ Internal report ISV-6/97 August 1996 Theoretical Investigations of Tomographic Methods used
More informationTemperature Patterns: Functions and Line Graphs
activity 3.1 Temperature Patterns: Functions and Line Graphs In this activity, you will work with examples in which curves obtained by joining known points of the graph of a function can help you understand
More informationCOUPLED BWR CALCULATIONS with the NUMERICAL NUCLEAR REACTOR SOFTWARE SYSTEM
Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) COUPLED BWR CALCULATIONS with the NUMERICAL
More informationSPE MS Multivariate Analysis Using Advanced Probabilistic Techniques for Completion Optimization
SPE-185077-MS Multivariate Analysis Using Advanced Probabilistic Techniques for Completion Optimization Bertrand Groulx, Verdazo Analytics; Jim Gouveia, Rose & Associates, LLP; Don Chenery, Verdazo Analytics
More informationGeostatistical Reservoir Characterization of McMurray Formation by 2-D Modeling
Geostatistical Reservoir Characterization of McMurray Formation by 2-D Modeling Weishan Ren, Oy Leuangthong and Clayton V. Deutsch Department of Civil & Environmental Engineering, University of Alberta
More informationFlow Around Nuclear Rod Bundles Simulations Based on RANS and LES Method Respectively
Proceedings of the World Congress on Mechanical, Chemical, and Material Engineering (MCM 2015) Barcelona, Spain July 20-21, 2015 Paper No. 285 Flow Around Nuclear Rod Bundles Simulations Based on RANS
More informationIdentification of Shielding Material Configurations Using NMIS Imaging
Identification of Shielding Material Configurations Using NMIS Imaging B. R. Grogan, J. T. Mihalczo, S. M. McConchie, and J. A. Mullens Oak Ridge National Laboratory, P.O. Box 2008, MS-6010, Oak Ridge,
More informationSTATISTICAL CALIBRATION: A BETTER APPROACH TO INTEGRATING SIMULATION AND TESTING IN GROUND VEHICLE SYSTEMS.
2016 NDIA GROUND VEHICLE SYSTEMS ENGINEERING and TECHNOLOGY SYMPOSIUM Modeling & Simulation, Testing and Validation (MSTV) Technical Session August 2-4, 2016 - Novi, Michigan STATISTICAL CALIBRATION: A
More informationIBM. Enterprise Systems Architecture/ Extended Configuration Principles of Operation. z/vm. Version 6 Release 4 SC
z/vm IBM Enterprise Systems Architecture/ Extended Configuration Principles of Operation Version 6 Release 4 SC24-6192-01 Note: Before you use this information and the product it supports, read the information
More informationImpact of lead free simulated repeated reflow on through hole reliability using AATC
Impact of lead free simulated repeated reflow on through hole reliability using AATC Multek Helmut.Kroener@de.multek.com +49 171 463 5431 February 07, 2006 ABRACI Sao Paulo RoHS Directive 2002/95/EC January
More informationEvaluation of CDA as A Standard Terminal Airspace Operation
Partnership for AiR Transportation Noise and Emission Reduction An FAA/NASA/TC/DOD/EPA-sponsored Center of Excellence Evaluation of CDA as A Standard Terminal Airspace Operation School of Aeronautics &
More informationSOFTWARE REQUIREMENTS SPECIFICATION FOR THE TRAC-M-SPECIFIC DATA MAP ROUTINE IN THE COUPLED TRAC-M/PARCS CODE. R. Matthew Miller, Thomas J.
PU/NE-00-9 SOFTWARE REQUIREMENTS SPECIFICATION FOR THE TRAC-M-SPECIFIC DATA MAP ROUTINE IN THE COUPLED TRAC-M/PARCS CODE R. Matthew Miller, Thomas J. Downar School of Nuclear Engineering Purdue University
More informationonlinecomponents.com
0.9 For FPC FPC connectors (0.3mm pitch) Back lock Y3B Series New FEATURES 1. Slim and low profile design (Pitch: 0.3 mm) The use of a back lock mechanism enables a 3.15 mm (with lever) low profile design.
More informationPhysics 1050 Experiment 2. Acceleration Due to Gravity
Acceleration Due to Gravity Prelab uestions! These questions need to be completed before entering the lab. Show all workings. Prelab 1: For a falling ball which bounces, draw the expected shape of the
More informationMichael Speiser, Ph.D.
IMPROVED CT-BASED VOXEL PHANTOM GENERATION FOR MCNP MONTE CARLO Michael Speiser, Ph.D. Department of Radiation Oncology UT Southwestern Medical Center Dallas, TX September 1 st, 2012 CMPWG Workshop Medical
More informationProblem 1. Lab #12 Solution
Lab #1 Solution Problem 1 Given Truss Roof Dead Load of 16 psf, Snow Live load of 16 psf, Truss spacing of 4" o.c. Lumber is No. DF-L Bolt holes are 7/" diameter, MC < 19%, Temp < 100 degree F, and Ci
More informationCharacterizing Touch Panel Sensor ESD Failure with IV-Curve TLP (System Level ESD)
Characterizing Touch Panel Sensor ESD Failure with IV-Curve TLP (System Level ESD) Wei Huang, Jerry Tichenor, David Pommerenke 2014 ESDA Exhibition Booth 606 Web: www.esdemc.com Email: info@esdemc.com
More informationNuclear Reactor "Pincell" Example
Nuclear Reactor "Pincell" Example In this example, we will create a simple 3D "pincell" that is common in many pressurized water reactor geometries. It is basically a very long rectangular prism with a
More informationMechanism Design using Creo Parametric 3.0
Mechanism Design using Creo Parametric 3.0 Overview Course Code Course Length TRN-4521-T 1 Day In this course, you will learn about creating mechanism connections, configuring the mechanism model, creating
More informationNuclear Data Capabilities Supported by the DOE NCSP
Nuclear Data Capabilities Supported by the DOE NCSP Symposium on Nuclear Data for Criticality Safety and Reactor Applications Rensselaer Polytechnic Institute April 27, 2011 The NCSP Mission & Vision 2
More informationExperience in Neutronic/Thermal-hydraulic Coupling in Ciemat
Madrid 2012 Experience in Neutronic/Thermal-hydraulic Coupling in Ciemat Miriam Vazquez (Ciemat) Francisco Martín-Fuertes (Ciemat) Aleksandar Ivanov (INR-KIT) Outline 1. Introduction 2. Coupling scheme
More informationTwo-Phase flows on massively parallel multi-gpu clusters
Two-Phase flows on massively parallel multi-gpu clusters Peter Zaspel Michael Griebel Institute for Numerical Simulation Rheinische Friedrich-Wilhelms-Universität Bonn Workshop Programming of Heterogeneous
More informationError Analysis, Statistics and Graphing
Error Analysis, Statistics and Graphing This semester, most of labs we require us to calculate a numerical answer based on the data we obtain. A hard question to answer in most cases is how good is your
More informationDAY 52 BOX-AND-WHISKER
DAY 52 BOX-AND-WHISKER VOCABULARY The Median is the middle number of a set of data when the numbers are arranged in numerical order. The Range of a set of data is the difference between the highest and
More informationJakarta International School 8 th Grade AG1
Jakarta International School 8 th Grade AG Practice Test - Green Unit : Graphing Name: Date: Score: 85 Goal 4: Students convert graphical, symbolic, and numerical representations of data. The points (-,)
More informationCombustionMaster Control Solutions. Unique Combustion Control for Gas and/or Oil-Fired Boilers
CombustionMaster Control Solutions Unique Combustion Control for Gas and/or Oil-Fired Boilers Unique Combustion Control Solution for Gas and/or Oil-Fired Boilers The CombustionMaster system from Rockwell
More informationExperiment 6. Snell s Law. Use Snell s Law to determine the index of refraction of Lucite.
Experiment 6 Snell s Law 6.1 Objectives Use Snell s Law to determine the index of refraction of Lucite. Observe total internal reflection and calculate the critical angle. Explain the basis of how optical
More informationMath and Feature Models of Assemblies
Math and Feature Models of Assemblies Start of series of 5 classes on math/cad models basic matrix representations and Feature-based Design constraint variation assembly sequence analysis Datum Flow Chain
More information