Session NG-I:
Theory and Methods
(Monday, October 23, p.m.)
NG-I/I1
J. Spanier
Research themes of broad transport applicability
(amc005)
NG-I/O1
T. Ueki, J.E. Hoogenboom, J.L. Kloosterman
Response Decomposition with Monte Carlo Correlated Coupling
(amc044)
NG-I/O2
T. Shuttleworth
The Geometrical Sensitivity Option in MCBEND
(amc121)
NG-I/O3
T.E. Booth
An alternative Monte Carlo method for the k-Eigenfunction?
(amc146)
NG-I/O4
J.E. Hoogenboom
Continuous Energy Adjoint Monte Carlo for Coupled Neutron-Photon Transport
(amc149)
NG-I/O5
A. Haghighat, J.C. Wagner
Application of A3MCNP to Radiation Shielding Problems
(amc211)
Session NG-II:
Code Status
(Monday, October 23, p.m.)
NG-II/I1
T. Mori, K. Okumura, Y. Nagaya
Status of JAERI’s Monte Carlo Code MVP for Neutron and Photon Transport Problems
(amc027)
NG-II/I2
M.B. Emmett
Current Status of the Oak Rdige Monte Carlo Shielding Codes
(amc076)
NG-II/I3
N. Smith, T. Shuttleworth, M. Grimstone, L. Hutton, M. Armishaw, A.Bird, N. France, S. Connolly
The Current Status and Future Plans for the Monte Carlo Codes MONK and MCBEND
(amc119)
NG-II/I4
E.C. Selcow, G.W. McKinney
MCNP Capabilities at the Dawn of the 21st Century: Neutron-gamma Applications
(amc188)
NG-II/I5
L. Maiorov, E. Gomin, M.I. Gurevich
ich
Status of MCU(amc203)
NG-II/I6
J.C Nimal, T. Vergnaud
TRIPOLI-3 A Neutron/Photon Monte Carlo Transport Code
(amc238)
Session NG-III:
Physics & Data
(Tuesday, October 24, a.m.)
NG-III/I1
R. C. Little, S. C. Frankle, M. C. White, R. MacFarlane, C. J. Werner, J. M. Campbell
Modern Nuclear Data for Monte Carlo Codes
(amc235)
NG-III/O1
J. D¸ abrowska, K. Drozdowicz, U. Woznicka
The MCNP code in planning and interpretation of thermal neutron pulsed experiments
(amc054)
NG-III/O2
J. Tickner
Modelling Detector Responses to Neutrons using MCNP
(amc059)
NG-III/O3
J.P. Both, J.C Nimal, Y. Peneliau
Water cross section sensitivity in the Naiade benchmark using TRIPOLI-4
(amc101)
NG-III/O4
P.A. Andresenko, M.R. Malkov
Simulation of thermal neutron transport processes directly from the Evaluated Nuclear Data Files
(amc116)
NG-III/O5
G. Hordósy, A. Keresztúri, Cs. Hegedus, P. Vértes
Importance of (g,n) reaction in the dynamic behaviour of Be reflected reactors
(amc171)
Session NG-IV:
Algorithms & Computational Science
(Tuesday, October 24, p.m.)
NG-IV/I1
K.W. Burn, G. Gualdrini, E. Nava
Variance Reduction with Multiple Responses
(amc092)
NG-IV/O1
T.J. Urbatsch, T.M. Evans, H. Lichtenstein
1-D Equilibrium Discrete Diffusion Monte Carlo
(amc043)
NG-IV/O2
C. Diop
Full Monte Carlo Particle Transport/Isotope Depletion Coupling
(amc118)
NG-IV/O3
J.L. Hutton
Use of a Hybrid Monte Carlo Technique for Power Shape Calculations
(amc122)
NG-IV/O4
O. Jacquet, X. Bay, L. Carraro
Evaluation of the Uncertainty in Eigenvalue Monte Carlo Calculations, Using Time Series Methodologies
(amc130)
NG-IV/O5
J. Miss, A. Nouri 1, O. Jacquet
Development and Comparison of Monte-Carlo Techniques for the Calculation of Loosely Coupled Systems
(amc131)
Session NG-V:
Experiments & Measurements
(Wednesday, October 25, a.m.)
NG-V/I1
B. Siebert
Sensitivity Analysis and Uncertainty Assessment in Applied Monte Carlo Particle Transport
(amc166)
NG-V/O1
B.T. Rearden, L.M. Petire, D.F. Hollenbach
Sensitivity and Uncertainty Analysis for Nuclear Criticality Safety Using KENO in the SCALE Code System
(amc231)
NG-V/O2
A. Fernandes, A. Vieira, I.C. Gonçalves, A. Ramalho
Monte-Carlo determination of the radiation field in the thermal column of the Portuguese Research Reactor
(amc050)
NG-V/O3
T. Aoyama, T. Sekine
Fission Rate Analysis in the Irradiation Test Subassemblies of Fast Reactor Using MCNP
(amc082)
NG-V/O4
T. Valentine
Benchmarking Monte Carlo Codes for Criticality Safety Using Subcritical Measurements
(amc018)
NG-V/O5
R.J. Tanner, D.T. Bartlett, L.G. Hager
Calculations of the Response of the NRPB Neutron Personal Dosemeter using MCNP ans Experimental Verification of those Calculations
(amc123)
Session NG-VI:
Applications
(Wednesday, October 25, a.m.)
NG-VI/I1
T. Goorley
Review of Industrial and Medical Applications that Utilize Coupled Neutron-Photon Monte Carlo Transport
(amc057)
NG-VI/O1
I.F. Gonçalves, A.G. Ramalho, I.C.Gonçalves, J. Salgado
MCNP Calculations for the shielding design of a beam tube to be installed at the Portuguese Research Reactor
(amc041)
NG-VI/O2
U. Fischer
Monte Carlo Applications in Fusion Neutronics
(amc052)
NG-VI/O3
F. Rahnema, S. Mosher, M. Pitts, P. Akhtar, D. Serghiuta
Continuous-Energy Monte Carlo Simulation of a Simplified CANDU Core Sub-region
(amc056)
NG-VI/O4
M. Maucec, P.H.G.M. Hendriks, R.J. de Meijer
Monte Carlo Simulation of Natural Gamma Ray Spectrometry for Underwater Surfaces
(amc096)
NG-VI/O5
B. Verboomen, A.Beeckmans. de West-Meerbeeck, Th. Aoust, and Ch. De Raedt
Monte Carlo Modelling of the Belgian Materials Testing Reactor BR2
(amc142)
Session NG-VII:
Benchmarks
(Thursday, October 26, a.m.)
NG-VII/I1
S. Sitaraman, R-T. Chiang, K. Asano, K. Koyabu
Benchmark for a 3D Monte Carlo Boiling Water Reactor Fluence Computational Package - MF3D
(
amc021)NG-VII/O1
U. Fischer, I. Kodeli, C. Konno, R. L. Perel
Intercomparison of Monte Carlo and SN Sensitivity Calculations for a 14 MeV Neutron Benchmark
(amc053)
NG-VII/O2
S.M. Zaritsky, N.I. Alexeyev, A.E. Glushkov, M.I. Gurevich, D.A. Shkarovsky
Comparison of calculations with benchmark experiments: validation of the MCU-4 code with ENDF/B-VI data library for tasks of neutron penetration through iron
(
amc065)NG-VII/O3
T. Goorley, S. Kiger, R. Zamenhof
Comparison of Snyder Head Phantom Models Used for Neutron Capture Therapy Benchmark Monte Carlo Dosimetry Calculations
(
amc074)NG-VII/O4
A. Polanski, V. Barashenkov, I. Puzynin, I. Rakhno, A. Sissakian
Monte Carlo modeling of fast sub-critical assembly with MOX fuel for research of accelerator driven systems
(amc168)
NG-VII/O5
Y.K. Lee
Evaluation of CRISTO II Storage Arrays Benchmark with TRIPOLI-4.2 Criticality Calculations
(amc180)
Session NG-VIII:
Graphics & Applications
(Thursday, October 26, a.m.)
NG-VIII/I1
R.A. Schwarz, L.L. Carter, V.E. Roetman, K.E. Hillesland
Current State of Monte Carlo Visualization Tools
(amc153)
NG-VIII/O1
T. Kugo
Conceptual Designing of a Reduced Moderation Pressurized Water Reactor by Use of MVP and MVP-BURN
(amc048)
NG-VIII/O2
M. Armishaw, A. Bird, H. Crofts, N. Smith
The Role of Graphical Supporting Tools for Monte Carlo Analysis
(amc120)
NG-VIII/O3
D.L. Bleuel, R.J. Donahue, B.A. Ludewigt, J. Vujic
Simulating Problems with Variable Sources via Post Processing of Individual Particle Tallies
(amc143)
NG-VIII/O4
Z. Karrien, C.C. Stoker, F. Reitsma
MCNP Modelling of HTGR Pebble-Type Fuel Elements
(amc150)
NG-VIII/O5
S.M. Bowman, J.E. Horwedel
KENO3D Visualization Tool for KENO V.a and KENO VI
(amc232)
NG-P (Poster Session)
Neutron-gamma contributed papers
(Wednesday, October 25, p.m.)
NG-P1
V.V. Korobeinikov
Universal approach for ADS blanket calculations by Monte Carlo method
(amc001)
NG-P2
T. Kato, T. Nakamura
Development of analytical method for bulk shielding calculation in a medium energy accelerator facility
(amc012)
NG-P3
H.J. Shim, C.S. Jang, Chang Hyo Kim
Monte Carlo Depletion Analysis of PWR Integral Fuel Burnable Absorbers by MCNAP
(amc025)
NG-P4
O. Sato, S. Mitake, H. Tsunoda
Application of Biasing Optimization Techniques to Monte Carlo Shielding Analysis of Transport Cask
(amc067)
NG-P5
L. Petrizzi, H. Iida, D. Valenza, P. Batistoni
Improvement and Benchmarking of the New Shutdown Dose Estimation Method by Monte Carlo Code
(amc097)
NG-P6
P.A. Androsenko, D.L. Joloudov, A.V. Kompaniyets, M.R. Malkov
Monte Carlo Simulation of Neutron and Photon Transport with Direct Utilization of Information from Evaluated Nuclear Data Files
(amc148)
NG-P7
W. Gudowski, J. Cetnar, J. Wallenius, K. Tucek
Simulation of nuclide transmutation with Monte-Carlo continuous energy burnup system (MCB)
(amc196)
NG-P8
R.-T. Chiang, S. Sitarman, K. Asano, K. Koyabu
Application of MCNP-based Software Package MF3D for BWR Radiation Damage Computations
(amc016)
NG-P9
D. Schlegel, S. Guldbakke
Why do we need TARGET ?
(amc037)
NG-P10
Y. Rugama, J.L. Munoz-Cobo, T.E. Valentine
Noise Method for Monitoring the Subcriticality in Accelerator Driven Systems
(amc073)
NG-P11
R.J. de Meijer, P.H.G.M. Hendriks, M. Maucec
Sediment-density Dependence of Natural Gamma Ray Spectra in a Borehole Geometry
(amc155)
NG-P12
E. Bourhis, S. Hachem, J.-P. Pignol, N. Iborra Brassart, J. Herault, P. Chauvel, D. Paul, R. Sabattier, and N. Breteau
The use of MCNP4B for Monte Carlo simulation of the dosimetry of 10B neutron capture enhancement of fast neutron
(amc173)
NG-P13
A. Rogov, Y. Pepyolyshev
Experimental and Monte Carlo study of the plastic scintillator performance for the current mode measurement at pulsed neutron sources
(amc177)
NG-P14
R. Cabezas, H. Yoriyaz, A. Santos, M. Yamaguchi
Monte Carlo Burnup Analysis of the Nuclear Research Reactor IEAR-1 Using MCNP-4B Code
(amc061)
NG-P15
H. Sawamura, K. Nishimura, S. Takahashi, J.S. Schweitzer
The Feasibility Study of Non-Radioactive Tracers for Monitoring Injected Water in Oil Reservoirs
(amc083)
NG-P16
S. Rollet
Neutronics and Shielding Analysis of Ignitor
(amc088)
NG-P17
J. Svarny
About the Application of MCNP4 Code in Nuclear Reactor Core Design Calculations
(amc094)
NG-P18
A. Vieira, I. C. Goncalves, A. Ramalho
Monte Carlo calculations for neutron and gamma radiation fields on a fast neutron irradiation device
(amc098)
NG-P19
M. Coeck, T. Aoust, F. Vermeersch, and H.A. Abderrahim
Shielding assessment of the MYRRHA accelerator driven system using the MCNP code
(amc139)
NG-P20
G. Hordósy, P. Vértes
Influence of gamma photons and thermal neutrons on reactor pressure vessel damage
(amc170)
NG-P21
S. Belousov, K. Ilieva
The MCNP Application vor VVER-1000 Shielding Calculation
(amc179)
NG-P22
J. Ghassoun, K. Ueki, A. Jehouani
The Fast and the Thermal Neutron Flux Distribution in TRIGA Reactor Shields by Monte Carlo Method
(amc195)
NG-P23
Victor Muratov and Alexsander Lopatkin
Numercal tests for the problem of U-Pu fuel burnup in fuel rod and polycell models using the MCNP code
(amc241)