Monte Carlo calculations of neutron number sprectra and buildup factors in infinite conical configurations / Millard L. Wohl.

Predictive equations for thermal neutron flux perturbation effects in cylinders /

Lynch, John H.
Peters, Lawrence E.
United States. National Aeronautics and Space Administration.
Lewis Research Center.

Prepared at Lewis Research Center."December 1968"--Cover.Includes bibliographical references (p. 21)...

M0322 and M0332 : FORTRAN programs for calculating neutron absorption in spheres distributed randomly /

Cantwell, R. M.
Bettis Atomic Power Laboratory
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.

"Contract AT-11-1-GEN-14.""October 1962."Includes bibliographical references (page 28).Mode of acces...

Monte Carlo methods for shield computation /

Goertzel, Gerald, 1919-
Kahn, H.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1951

Work performed at the Oak Ridge National Laboratory."February 22, 1950."Title from cover.Includes bi...

Monte Carlo studies of gamma-ray and neutron transport in infinite homogeneous media. /

Fessler, Theodore E.
Wohl, Millard L.
United States. National Aeronautics and Space Administration.

Cover title."November 1961."Mathematics; Physics, nuclear and particle; Power sources, supplementary...

Contents

January 2008

The Monte Carlo method is being widely used to solve neutron transport problems in nuclear reactor c...

A Monte Carlo calculation of air-scattered neutrons /

Zerby, C. D.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Applied Nuclear Physics Division.

January 1957

"Date issued: May 24, 1957."At head of title: Applied Nuclear Physics Division.Includes bibliographi...

Neutron self-shielding factors for multiple-body concentric cylindrical configurations

Semlar, Thor T.
United States. National Aeronautics and Space Administration.

Cover title."September 1964."Includes bibliographical references.Mode of access: Internet

Experimental neutron flux distribution in a graphite assembly with an internal cavity / Thomas A. Fox, Donald F. Shook, Robert A. Mueller and Daniel Fieno.

Fox, Thomas A.
Fieno, Daniel.
Mueller, Robert A.
Shook, Donald F.
United States. National Aeronautics and Space Administration.

Cover title."October 1962."Physics, nuclear and particle; Propulsion systems, nuclear.Includes bibli...

Monte Carlo methods and their application to neutron transport problems /

Spanier, Jerome, 1930-
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...

A monte carlo code for the transport of neutrons /

Baxter, William V.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Physics and Mathematics (TID-4500, 15th Ed.).""Printed for the United States Atomic Energy Commissi...

TRAC-1 : a Monte Carlo Philco-2000 program for the calculation of neutron capture probabilities /

Berwind, H. J.
Spanier, Jerome, 1930-
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"UC-32: Mathematics and Computers; TID-4500 (16th Edition).""Contract AT-11-1-GEN-14.""March 1961."I...

A monte carlo study of resonance escape probability in heterogeneous slab lattices containing resonant absrobers and scatterers /

Schneider, Harold.
Sroub, Kevin J.
Levitt, Leo.
United States. National Aeronautics and Space Administration.

Cover title."April 1962."Physics, nuclear and particle; Power sources, supplementary; Propulsion sys...

A Monte Carlo calculation of the neutron flux from a monoenergetic point source in air /

Mehl, C. R.
U.S. Atomic Energy Commission.
Sandia Corporation.

January 1959

Results of a calculation of neutron transport through air are presented. Neutron flux and angular di...

Neutron flux distribution calculation using the P(3) spherical harmonic method /

Weil, J.W.
Knolls Atomic Power Laboratory.
U.S. Atomic Energy Commission.

January 1954

"July 10, 1954."Includes bibliographical references (pages 27-28).U.S. Atomic Energy Commission Cont...

Neutron blanket calculations for thermonuclear reactors, II /

Bell, George I., 1926- author.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

"United States Atomic Energy Commission Contract W-7405-ENG.36"--Cover."LA-4131-MS ; UC-20, Controll...

Predictive equations for thermal neutron flux perturbation effects in cylinders /

Lynch, John H.
Peters, Lawrence E.
United States. National Aeronautics and Space Administration.
Lewis Research Center.

Prepared at Lewis Research Center."December 1968"--Cover.Includes bibliographical references (p. 21)...

M0322 and M0332 : FORTRAN programs for calculating neutron absorption in spheres distributed randomly /

Cantwell, R. M.
Bettis Atomic Power Laboratory
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.

"Contract AT-11-1-GEN-14.""October 1962."Includes bibliographical references (page 28).Mode of acces...

Monte Carlo methods for shield computation /

Goertzel, Gerald, 1919-
Kahn, H.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1951

Work performed at the Oak Ridge National Laboratory."February 22, 1950."Title from cover.Includes bi...

Monte Carlo studies of gamma-ray and neutron transport in infinite homogeneous media. /

Fessler, Theodore E.
Wohl, Millard L.
United States. National Aeronautics and Space Administration.

Cover title."November 1961."Mathematics; Physics, nuclear and particle; Power sources, supplementary...

Contents

January 2008

The Monte Carlo method is being widely used to solve neutron transport problems in nuclear reactor c...

A Monte Carlo calculation of air-scattered neutrons /

Zerby, C. D.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory Applied Nuclear Physics Division.

January 1957

"Date issued: May 24, 1957."At head of title: Applied Nuclear Physics Division.Includes bibliographi...

Neutron self-shielding factors for multiple-body concentric cylindrical configurations

Semlar, Thor T.
United States. National Aeronautics and Space Administration.

Cover title."September 1964."Includes bibliographical references.Mode of access: Internet

Experimental neutron flux distribution in a graphite assembly with an internal cavity / Thomas A. Fox, Donald F. Shook, Robert A. Mueller and Daniel Fieno.

Fox, Thomas A.
Fieno, Daniel.
Mueller, Robert A.
Shook, Donald F.
United States. National Aeronautics and Space Administration.

Cover title."October 1962."Physics, nuclear and particle; Propulsion systems, nuclear.Includes bibli...

Monte Carlo methods and their application to neutron transport problems /

Spanier, Jerome, 1930-
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...

A monte carlo code for the transport of neutrons /

Baxter, William V.
U.S. Atomic Energy Commission.
Savannah River Laboratory.
E.I. du Pont de Nemours & Company.

"Physics and Mathematics (TID-4500, 15th Ed.).""Printed for the United States Atomic Energy Commissi...

TRAC-1 : a Monte Carlo Philco-2000 program for the calculation of neutron capture probabilities /

Berwind, H. J.
Spanier, Jerome, 1930-
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"UC-32: Mathematics and Computers; TID-4500 (16th Edition).""Contract AT-11-1-GEN-14.""March 1961."I...

A monte carlo study of resonance escape probability in heterogeneous slab lattices containing resonant absrobers and scatterers /

Schneider, Harold.
Sroub, Kevin J.
Levitt, Leo.
United States. National Aeronautics and Space Administration.

Cover title."April 1962."Physics, nuclear and particle; Power sources, supplementary; Propulsion sys...

A Monte Carlo calculation of the neutron flux from a monoenergetic point source in air /

Mehl, C. R.
U.S. Atomic Energy Commission.
Sandia Corporation.

January 1959

Results of a calculation of neutron transport through air are presented. Neutron flux and angular di...

Neutron flux distribution calculation using the P(3) spherical harmonic method /

Weil, J.W.
Knolls Atomic Power Laboratory.
U.S. Atomic Energy Commission.

January 1954

"July 10, 1954."Includes bibliographical references (pages 27-28).U.S. Atomic Energy Commission Cont...

Neutron blanket calculations for thermonuclear reactors, II /

Bell, George I., 1926- author.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

"United States Atomic Energy Commission Contract W-7405-ENG.36"--Cover."LA-4131-MS ; UC-20, Controll...

Predictive equations for thermal neutron flux perturbation effects in cylinders /

Lynch, John H.
Peters, Lawrence E.
United States. National Aeronautics and Space Administration.
Lewis Research Center.

Prepared at Lewis Research Center."December 1968"--Cover.Includes bibliographical references (p. 21)...

M0322 and M0332 : FORTRAN programs for calculating neutron absorption in spheres distributed randomly /

Cantwell, R. M.
Bettis Atomic Power Laboratory
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.

"Contract AT-11-1-GEN-14.""October 1962."Includes bibliographical references (page 28).Mode of acces...

Monte Carlo methods for shield computation /

Goertzel, Gerald, 1919-
Kahn, H.
Oak Ridge National Laboratory.
U.S. Atomic Energy Commission.

January 1951

Work performed at the Oak Ridge National Laboratory."February 22, 1950."Title from cover.Includes bi...

Monte Carlo calculations of neutron number sprectra and buildup factors in infinite conical configurations / Millard L. Wohl.

Abstract

Extracted data

Monte Carlo calculations of neutron number sprectra and buildup factors in infinite conical configurations / Millard L. Wohl.

Abstract

Extracted data

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