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Title: A novel method for the design and selection of neutron-attenuating media

Journal Article · · Annals of Nuclear Energy

Not Available

Sponsoring Organization:
USDOE
OSTI ID:
1815111
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: C Vol. 160; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United Kingdom
Language:
English

References (21)

The mechanism of the (n, 2n) reaction journal November 1963
MOCUM: A two-dimensional method of characteristics code based on constructive solid geometry and unstructured meshing for general geometries journal August 2012
Neutron shielding design for 241Am–Be neutron source considering different sites to achieve maximum thermal and fast neutron flux using MCNPX code journal September 2013
A novel method for designing the moderator of accelerator-driven neutron source journal November 2019
Validation and Application of MCNP and TORT Source Generation Codes journal September 2017
An approach to fuel development and qualification journal September 2007
Enhancing neutron beam production with a convoluted moderator
  • Iverson, E. B.; Baxter, D. V.; Muhrer, G.
  • Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 762 https://doi.org/10.1016/j.nima.2014.04.047
journal October 2014
A high performance neutron moderator design journal September 2015
The fundamental neutron physics facilities at NIST
  • Dewey, M. S.; Arif, M.; Gentile, T. R.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 241, Issue 1-4 https://doi.org/10.1016/j.nimb.2005.07.028
journal December 2005
Neutron Moderator Development Research at the Low Energy Neutron Source journal January 2012
Optimization of an Am-Be neutron source shield design by advanced materials using MCNP code journal May 2019
Measurements of Neutron Attenuation through Iron and Concrete at ISIS journal March 2000
Importance Determination Method for Geometry Splitting with Russian Roulette in Monte Carlo Calculations of Thick and Complicated Core Shielding Structure journal October 1995
Designing of the 14 MeV neutron moderator for BNCT journal September 2012
Monotone Piecewise Cubic Interpolation journal April 1980
Measurements of Neutron Spectra in Water, Polyethylene, and Zirconium Hydride journal February 1961
The Remodeling and Basic Characteristics of the Heavy Water Neutron Irradiation Facility of the Kyoto Univesity Research Reactor, Mainly for Neutron Capture Therapy journal September 2000
Neutron Shielding of Underground Nuclear Explosives journal July 1971
Thermal-Neutron Radiography with a Sealed-Tube Neutron Generator and Water Moderator journal June 1972
Compendium of Material Composition Data for Radiation Transport Modeling report March 2011
Low dimensional neutron moderators for enhanced source brightness journal January 2014

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