Boundary And Interface Conditions For Approximate Solutions Of The Neutron Transport Equation.

Numerical solution of transient and steady-state neutron transport problems /

Carlson, Bengt G.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1959

"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-2260 ; Physics and Mathematics ;...

One-speed Neutron Transport Problems In Plane Geometry.

Mccormick, Norman Joseph

January 1965

Ph.D.PhysicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://deepblue.lib....

DIFF, a code to prepare neutron diffusion theory parameters from the results of the code WDSN.

Spinks, N
Manning, G

March 1967

With a solution of the multigroup neutron transport equation available for a problem in one dimensio...

On the boundary conditions for the neutron transport equation

Saracco P.
Chentre N.
Dulla S.
Ravetto P.

January 2020

The solution of the linear transport equation used for the study of neutral particle fields requires...

Finite-element Solution Of The Two-dimensional Neutron Transport Equation.

Yehnert, Carl Eugene

January 1978

PhDEnergyNuclear physicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://d...

The Application Of The Finite Element Method To The Neutron Transport Equation.

Martin, William Russell

January 1976

Ph.D.Applied SciencesEnergyNuclear engineeringUniversity of Michigan, Horace H. Rackham School of Gr...

Solutions of the two-group neutron transport equation : part I : technical report.

Metcalf, Dale Robert.
Zweifel, Paul Frederick

January 1968

http://deepblue.lib.umich.edu/bitstream/2027.42/6594/5/bac9527.0001.001.pdfhttp://deepblue.lib.umich...

Boundary and interface function method for one dimensional neutron transport

Antolak, A.J.
Bareiss, E.H.

November 1979

A new numerical method, the Boundary and Interface Function (BIF) Method, for solving the one-dimens...

An Explicitly-Interfaced Finite Element Solution of the Neutron Transport Equation.

Lorence, Leonard Joseph, Jr.

January 1984

A numerical solution of the first-order, mono-energetic neutron transport equation is found by the f...

Solutions Of The One-speed Neutron Transport Equation In Plane Geometry.

Mendelson, Max Richard

January 1964

PhDEnergyNuclear physicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://d...

Variational solutions to the neutron transport equation in P[subscript N] approximation

Dias, Mahendra Prinath

January 1982

Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...

Solutions of the two-group neutron transport equation : part II : technical report.

Metcalf, Dale Robert.
Zweifel, Paul Frederick

January 1968

http://deepblue.lib.umich.edu/bitstream/2027.42/6595/5/bac9527.0002.001.pdfhttp://deepblue.lib.umich...

A solution of the neutron transport equation :

Certaine, J.
U.S. Atomic Energy Commission. New York Operations Office.
Nuclear Development Corporation of America.

"Nuclear Development Associates, Inc., White Plains, New York.""Work performed under Contract AT(30-...

Neutron transport theory as a singular integral equation

Lewins, J
Cambridge Univ. (United Kingdom). Dept. of Engineering

January 1984

SIGLEAvailable from British Library Document Supply Centre- DSC:9106.17(CUED/A-NUCL/TR--3) / BLDSC -...

Simplified PN and AN methods in neutron transport

CIOLINI, RICCARDO
COPPA G. G. M
MONTAGNINI B
RAVETTO P.

January 2003

The paper deals with general properties of the odd-order SP N equations. The equivalence between the...

Numerical solution of transient and steady-state neutron transport problems /

Carlson, Bengt G.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1959

"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-2260 ; Physics and Mathematics ;...

One-speed Neutron Transport Problems In Plane Geometry.

Mccormick, Norman Joseph

January 1965

Ph.D.PhysicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://deepblue.lib....

DIFF, a code to prepare neutron diffusion theory parameters from the results of the code WDSN.

Spinks, N
Manning, G

March 1967

With a solution of the multigroup neutron transport equation available for a problem in one dimensio...

On the boundary conditions for the neutron transport equation

Saracco P.
Chentre N.
Dulla S.
Ravetto P.

January 2020

The solution of the linear transport equation used for the study of neutral particle fields requires...

Finite-element Solution Of The Two-dimensional Neutron Transport Equation.

Yehnert, Carl Eugene

January 1978

PhDEnergyNuclear physicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://d...

The Application Of The Finite Element Method To The Neutron Transport Equation.

Martin, William Russell

January 1976

Ph.D.Applied SciencesEnergyNuclear engineeringUniversity of Michigan, Horace H. Rackham School of Gr...

Solutions of the two-group neutron transport equation : part I : technical report.

Metcalf, Dale Robert.
Zweifel, Paul Frederick

January 1968

http://deepblue.lib.umich.edu/bitstream/2027.42/6594/5/bac9527.0001.001.pdfhttp://deepblue.lib.umich...

Boundary and interface function method for one dimensional neutron transport

Antolak, A.J.
Bareiss, E.H.

November 1979

A new numerical method, the Boundary and Interface Function (BIF) Method, for solving the one-dimens...

An Explicitly-Interfaced Finite Element Solution of the Neutron Transport Equation.

Lorence, Leonard Joseph, Jr.

January 1984

A numerical solution of the first-order, mono-energetic neutron transport equation is found by the f...

Solutions Of The One-speed Neutron Transport Equation In Plane Geometry.

Mendelson, Max Richard

January 1964

PhDEnergyNuclear physicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://d...

Variational solutions to the neutron transport equation in P[subscript N] approximation

Dias, Mahendra Prinath

January 1982

Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...

Solutions of the two-group neutron transport equation : part II : technical report.

Metcalf, Dale Robert.
Zweifel, Paul Frederick

January 1968

http://deepblue.lib.umich.edu/bitstream/2027.42/6595/5/bac9527.0002.001.pdfhttp://deepblue.lib.umich...

A solution of the neutron transport equation :

Certaine, J.
U.S. Atomic Energy Commission. New York Operations Office.
Nuclear Development Corporation of America.

"Nuclear Development Associates, Inc., White Plains, New York.""Work performed under Contract AT(30-...

Neutron transport theory as a singular integral equation

Lewins, J
Cambridge Univ. (United Kingdom). Dept. of Engineering

January 1984

SIGLEAvailable from British Library Document Supply Centre- DSC:9106.17(CUED/A-NUCL/TR--3) / BLDSC -...

Simplified PN and AN methods in neutron transport

CIOLINI, RICCARDO
COPPA G. G. M
MONTAGNINI B
RAVETTO P.

January 2003

The paper deals with general properties of the odd-order SP N equations. The equivalence between the...

Numerical solution of transient and steady-state neutron transport problems /

Carlson, Bengt G.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1959

"Contract W-7405-ENG.36 with the U.S. Atomic Energy Commission.""LA-2260 ; Physics and Mathematics ;...

One-speed Neutron Transport Problems In Plane Geometry.

Mccormick, Norman Joseph

January 1965

Ph.D.PhysicsUniversity of Michigan, Horace H. Rackham School of Graduate Studieshttp://deepblue.lib....

DIFF, a code to prepare neutron diffusion theory parameters from the results of the code WDSN.

Spinks, N
Manning, G

March 1967

With a solution of the multigroup neutron transport equation available for a problem in one dimensio...

Boundary And Interface Conditions For Approximate Solutions Of The Neutron Transport Equation.

Abstract

Extracted data

Boundary And Interface Conditions For Approximate Solutions Of The Neutron Transport Equation.

Abstract

Extracted data

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