Monte Carlo model of a low-energy neutron interrogation system for detecting fissile material

Monte Carlo model of a low-energy neutron interrogation system for detecting fissile material

Includes bibliographical references (p. 66-67).

Bibliographic Details
Main Author:	Johnson, Erik D., Ph. D. Massachusetts Institute of Technology
Other Authors:	Richard C. Lanza.
Format:	Thesis
Language:	eng
Published:	Massachusetts Institute of Technology 2008
Subjects:	Nuclear Science and Engineering.
Online Access:	http://hdl.handle.net/1721.1/41262

Similar Items

Characterization of fissile material using low energy neutron interrogation
by: Padilla, Eduardo A
Published: (2008)

Fissile material detection using neutron time-correlations from photofission
by: Soltz, R. A., et al.
Published: (2020)

Temperature-dependent symmetry energy of neutron-rich thermally fissile nuclei
by: Quddus, Abdul, et al.
Published: (2019)

A system for the detection of concealed nuclear weapons and fissile material aboard cargo cotainerships
by: Gallagher, Shawn P., S.M. Massachusetts Institute of Technology
Published: (2006)

GPU-Oriented Algorithms for Continuous Energy Monte Carlo Neutron Transport
by: Ridley, Gavin
Published: (2024)

Acceleration methods for Monte Carlo particle transport simulations
by: Li, Lulu, Ph. D Massachusetts Institute of Technology
Published: (2017)

Remote detection of fissile material : Cherenkov counters for gamma detection
by: Erickson, Anna S
Published: (2013)

Quantum Monte Carlo for accurate energies and materials design
by: Saritas, Kayahan
Published: (2017)

Monte Carlo methods, models, and applications for the advanced neutron source
by: Redmond, Everett Lee
Published: (2005)

Monte Carlo simulation of neutron shielding for proton therapy facilities
by: Folkert, Michael R. (Michael Ryan), 1975-
Published: (2010)

Calculating reaction rate derivatives in Monte Carlo neutron transport/
by: Harper, Sterling (Sterling M.)
Published: (2017)

Monte Carlo simulation model for electromagnetic scattering from vegetation and inversion of vegetation parameters
by: Wang, Li-Fang, Ph. D. Massachusetts Institute of Technology
Published: (2007)

Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
by: Omar, Muhammad Rabie
Published: (2020)

KAJIAN KOMPUTASI DISTRIBUSI STATISTIK FLUKS NEUTRON DENGAN METODE MONTE CARLO
by: , Tuti Purwoningsih, et al.
Published: (2011)

Multi-core performance studies of a Monte Carlo neutron transport code
by: Siegel, A. R., et al.
Published: (2017)

Computational treatments for neutron resonance elastic scattering in Monte Carlo nuclear simulations
by: Tran, Vivian Y
Published: (2017)

Simulasi riwayat neutron epitermal pada terapi tangkapan neutron oleh boron dengan metode Monte Carlo
by: , RAZALI, et al.
Published: (1998)

Cumulative migration method for computing multi-group transport cross sections and diffusion coefficients with Monte Carlo calculations
by: Liu, Zhaoyuan,Ph. D.Massachusetts Institute of Technology.
Published: (2021)

Computational methods for efficient nuclear data management in Monte Carlo neutron transport simulations
by: Walsh, Jonathan A. (Jonathan Alan)
Published: (2015)

Improvement of neutron collimator design for thermal neutron radiography using Monte Carlo-Particle transport code version 5
by: Supramaniam, Thiagu
Published: (2007)

Monte Carlo model for designing fluorescent materials in a spectral filter
by: Ging, Justin D. (Justin Daniel), 1976-
Published: (2014)

Quantum Monte Carlo Calculations for Minimum Energy Structures
by: Wagner, Lucas K., et al.
Published: (2010)

A Quantum Monte Carlo method at fixed energy
by: Farhi, Edward, et al.
Published: (2016)

Multiple characterization of some glassy-alloys as photon and neutron shields: in-silico Monte Carlo investigation
by: Perişanoğl, U., et al.
Published: (2021)

Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations
by: Lund, Amanda L., et al.
Published: (2017)

On-the-fly Doppler broadening using multipole representation for Monte Carlo simulations on heterogeneous clusters
by: Xu, Sheng, S.M. Massachusetts Institute of Technology
Published: (2014)

Low variance methods for Monte Carlo simulation of phonon transport
by: Péraud, Jean-Philippe M. (Jean-Philippe Michel)
Published: (2012)

Low-Variance Monte Carlo Simulation of Thermal Transport in Graphene
by: Landon, Colin Donald, et al.
Published: (2017)

Sequential Monte Carlo in sequence
by: Nur Nabihah Rusyda, Roslan, et al.
Published: (2022)

A Simulation on Desired Neutron Flux for The Boron Neutron Capture Therapy (BNCT) Purpose by Using Monte Carlo N-Particle (MCNPX)
by: S., Shalbi, et al.
Published: (2020)

Feasibility analysis of scanning 100% of maritime cargo containers for fissile material
by: Foley, William E., III
Published: (2009)

Prompt gamma neutron activation analysis (PGNAA) of hydrocarbons: A monte carlo study with GEANT4
by: Lam, Yihua, et al.
Published: (2010)

Monte Carlo examination of common approaches for detecting response styles
by: Fan, Qianqian
Published: (2019)

Systems-based analysis of a ship borne approach for the detection of fissile material concealed in cargo containers
by: Broderick, Brett P
Published: (2006)

Monte Carlo study of coherent scattering effects of low-energy charged particle transport in Percus-Yevick liquids
by: Tattersall, Wade J., et al.
Published: (2015)

Optimization and Monte Carlo modeling of bundle divertors
by: Yang, T.F., et al.
Published: (2015)

A low order acceleration scheme for solving the neutron transport equation
by: Li, Lulu, Ph. D Massachusetts Institute of Technology
Published: (2014)

Low voltage reliability equivalent using monte-carlo simulation technique
by: Noorfatin Farhanie, Mohd Fauzi, et al.
Published: (2019)

Low Earth Orbit Stability Analysis Using Monte-Carlo Techniques
by: Appel, Grant F.
Published: (2024)

Low-noise Monte Carlo simulation of the variable hard sphere gas
by: Radtke, Gregg A., et al.
Published: (2011)