Highly Perturbed Operational Test Configurations at the WSMR Fast Burst Reactor

Open Access

Issue		EPJ Web of Conferences Volume 106, 2016 ISRD 15 – International Symposium on Reactor Dosimetry


Article Number		01007
Number of page(s)		9
Section		Dosimetry in Research and Test Reactors and in Accelerators
DOI		https://doi.org/10.1051/epjconf/201610601007
Published online		03 February 2016

J.L. Meason, H.L. Wright, J.C. Hogan, J.T. Harvey, “The Neutron Spectral Distribution from a Godiva Type Critical Assembly”, IEEE NS-22, No 6 (1975) [Google Scholar]
T. M. Flanders, M.H. Sparks, “Calculated Neutron Spectra of Fast Pulsed Reactors”, Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, Strasbourg, France, Kluwer Academic Publishers (1990) [Google Scholar]
T.M. Flanders, M.H. Sparks, W.W. Sallee, “Radiation Environment Produced by the White Sands Missile Range MoLLY-G Reactor”, Proceedings of the Physics, Safety, and Applications of Pulse Reactors International Embedded Topical Meeting, ANS (1994) [Google Scholar]
X-5 Monte Carlo Team, “MCNP – A General Purpose Monte Carlo N-Particle Transport Code, Version 5”, LA-UR-03-1987, Los Alamos National Laboratory, Los Alamos, NM (2003) [Google Scholar]
J.A. Grundl, C.M. Eisenhauer, “Compendium of Benchmark Neutron Fields for Reactor Dosimetry”, NBSIR 85-3151, U.S. Department of Commerce (1986) [Google Scholar]
V.V. Verbinski, N.A. Lurie, V.C. Rodgers, “Threshold Foil Measurements of Reactor Neutron Spectra for Radiation Damage Applications”, Nucl. Sci. Eng., 65 (1978) [Google Scholar]
“Standard Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation Hardness Testing of Electronics”, ASTM Standard Practice E722-09^ε1, American Society for Testing and Measurement, West Conshohocken, PA (2013) [Google Scholar]
M.H. Sparks, W.W. Sallee, T.M. Flanders, “Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments”, Reactor Dosimetry: 12^th International Symposium, STP 1490, ASTM International (2008) [Google Scholar]
W.N. McElroy, S. Bert, T. Crockett, R.G. Hawkins, “SAND-II, A Computer Automated Iterative Method for Neutron Flux Determination by Foil Activation”, AFWL-TR-41, Vol. I–IV (1967) [Google Scholar]
P.J. Griffin, J.G. Kelly, T.F. Luera, “SNL-RML Recommended Dosimetry Cross Section Compendium”, SAND92-0094, Sandia National Laboratories, Albuquerque, NM (1994) [Google Scholar]
D.T. Ingersoll, R.W. Roussin, C.Y. Fu, J.E. White, “DABL69, A Broad-Group Neutron/Photon Cross-Section Library for Defense Nuclear Applications”, ORNL/TM-10568, Oak Ridge National Laboratory, Oak Ridge, TN (1989) [Google Scholar]
D.E. Bartine, J.D. Knight, J.V. Pace III, R. Roussin, “Production and Testing of the DNA Few-Group Coupled Neutron-Gamma Cross Section Library”, ORNL/TM-4840, Oak Ridge National Laboratory, Oak Ridge, TN (1977) [Google Scholar]
“Measurement of Absorbed Dose of Neutrons, and of Mixtures of Neutrons and Gamma Rays”, Handbook 78, U.S. Department of Commerce, National Bureau of Standards, Washington, DC (1961) [Google Scholar]
NCRP Report No. 38, “Protection Against Neutron Radiation”, National Council on Radiation Protection and Measurements, Washington, DC (1971) [Google Scholar]
ICRP Publication 21, “Data for Protection Against Ionizing Radiation from External Sources”, Pergamon Press, Oxford (1973) [Google Scholar]
ICRP Publication 74, “Conversion Coefficients for use in Radiological Protection against External Radiation”, Pergamon Press, Oxford (1996) [Google Scholar]
ANSI/ANS-6.1.1-77, American Nuclear Society, LaGrange Park, IL (1977) [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.