INIS Repository Search - Results for the query - DEI:"NEUTRON TRANSPORT THEORY"
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http://inis.iaea.org/Search/search.aspx?orig_q=RN:23006286
Ray-tracing in complicated geometriesWeiss, Z. (Buero fuer Angewandte Mathematik, Rodenbach (Germany)); Ball, G. (Atomic Energy Corp. of South Africa Ltd., Pretoria (South Africa))</br>An algorithm is presented for merging the results of neutron ray-tracing in simpler geometries, into which a given target geometry has been previously decomposed. The algorithm automatically numbers regions in the target geometry...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7247503
Discrete eigenvalue problem for azimuthally dependent transport theoryShultis, J.K. (Kansas State Univ., Manhattan, KS); Hill, T.R.</br>The discrete eigenvalue problem associated with the one-speed azimuthal Fourier harmonics in plane geometry is discussed. An explicit expression, well-suited to numerical evaluation, is given for the dispersion function, and the reality...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16081105
Direct and indirect computation of the transport equation eigenvaluesPerel, R.L.; Wagschal, J.J. (Hebrew Univ., Jerusalem (Israel). Racah Inst. of Physics)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:27069562
On the index of the eigenvalue of a transport operatorKuang, Z.; Yang, M. (China Inst. of Atomic Energy, Beijing (China))</br>The index of the eigenvalue of the monoenergetic neutron transport operator is studied under the assumptions of homogeneity and boundedness of the medium and of isotropy of scattering. It is shown that all isolated real eigenvalues...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:23067700
Transport of neutrons in double random mediaRonen, Y. (Ben-Gurion Univ. of the Negev, Beersheba (Israel))</br>In this paper, we will address the problem of the transport of neutron in these double-random media. The key point in our approach lies in the assumption that random treatment is valid to this types of problems
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22062479
A family of transport equations in neutron transport theoryPrinja, A.K. (New Mexico Univ., Albuquerque, NM (USA). Dept. of Chemical and Nuclear Engineering)</br>The backward formulation of problems in neutron transport is considered. Boundary conditions are developed from the adjoint system which in turn is rigorously obtained from a variational principle. The variational principle is derived...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15028976
ANISN - Presentation and user's manualBastos, W.S. (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil))</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9418468
Point kinetics as an asymptotic representation of space-, energy-, and angle-dependent reactor kineticsDorning, J.; Spiga, G. (Univ. of Illinois, Urbana)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16056462
Multiple collision solutions for time-dependent neutron transport in slabs of finite thicknessWindhofer, P. (Oesterreichisches Forschungszentrum Seibersdorf G.m.b.H. Inst. fuer Reaktorsicherheit)</br>Oesterreichisches Forschungszentrum Seibersdorf G.m.b.H</br>Multiple collision solutions of the time-, space-, and angledependent neutron transport equation in slab geometry are given. Two different monodirectional sources have been used: Firstly, a delta(t)-shaped pulse of neutrons (delta(t):...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26051461
Complex eigenvalue spectrum of the monoenergetic neutron transport operatorQing, X.B. (Chalmers Univ. of Technology, Goteborg (Sweden))</br>It is proven that the monoenergetic neutron transport operator in the case of a spherically symmetric, isotropically scattering sphere with a cavity in a large body has infinitely many complex time eigenvalues. 15 refs
http://inis.iaea.org/Search/search.aspx?orig_q=RN:27069561
An asymptotic expansion theorem in transport theorySong, D. (Xi'an Jiaotong Univ. (China))</br>This paper is devoted to discussing neutron transport system in a finite convex body with continuous energy bounded away from the origin. Under the assumptions that all the cross sections are continuous, it is shown, by virtue of...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5096065
Computational complexity in multidimensional transport theory calculations. Progress report, September 1, 1972--August 31, 1973Bareiss, E.H.; Abu-Shumays, I.K.</br>Northwestern Univ., Evanston, Ill. (USA)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21092098
Smoothing effects in neutronic theoryMokhtar-Kharroubi, M. (Besancon Univ., 25 (France))</br>We study the L<sup>p</sup> regularity for a series of operators in constant use in neutronic theory. An application to some classical transport theory problems is given
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26051463
Description of the real point spectrum for a class of neutron transport operatorsLatrach, K. (Universite de Franche, Besancon (France))</br>The present paper deals with the fine structure of the real point spectrum of a class of transport operators with unsymmetric scattering kernels. The author gives necessary and sufficient conditions for existence, finiteness and sufficient...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8299545
Homogenization of linear transport problemsWilliams, M.</br>New York Univ., N.Y. (USA)</br>The physical theory of the forward and backward linear transport equations is discussed especially as it applies to a nuclear reactor. Asymptotic expansions are carried out for these equations in the presence of ''fast'' spatial heterogeneities...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13678661
The publications of Boris Davison and some reminiscences of the manWilliams, M.M.R. (ed.) (Queen Mary Coll., London (UK). Dept. of Nuclear Engineering); Kushneriuk, S.A.; Gay, B.; Watson, W.H.; Peierls, R.E.</br>A bibliography and tribute to Boris Davison is presented. The bibliography of his works takes the form of the listing of contents from 5 volumes of his written work, published by Atomic Energy of Canada Ltd. The five volumes cover...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16033019
Trace theorems for neutronic functions spacesCessenat, M. (CEA, Centre d'Etude de Limiel-Valenton, 94 - Villeneuve-Saint-Georges (France))</br>We give two general trace theorems for functions used in transport theory
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17061056
Spectral theory of the neutron transport operatorMokhtar-Kharroubi, M. (Paris-6 Univ., 75 (France). Lab. d'Analyse Numerique)</br>We give a complete description of the real point spectrum of the transport operator for a positive collision operator: necessary and sufficient condition of existence and of finiteness, behaviour of eigenvalues with the size of the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7252126
Determination of diffusion parameters using response matrix theoryPryor, R.J.; Sicilian, J.M. (Savannah River Lab., Aiken, SC)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48103667
Effect of fractional parameter on neutron transport in finite disturbed reactors with quadratic scatteringSallah, M. (Faculty of Science, Mansoura University, Mansoura 35516, (Egypt)); Margeanu, C. A. (Institute for Nuclear Research, RATEN ICN Pitesti, (Romania)), E-mail: msallahd@mans.edu.eg</br>Faculty of Science, Mansoura University, Mansoura 35516, (Egypt)</br>The space-fractional neutron transport equation is used to describe the neutrons transport in finite disturbed reactors. It is approximated using the Pomraning-Eddington technique to yield two space-fractional differential equations,...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15028452
Approximation procedures for the angular variable in neutronic distributionJachic, J. (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil))</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:30000938
Neutronics study and analysis of a multifunctional blanketXiao Bingjia; Qiu Lijian (Academia Sinica, Hefei, AH (China). Inst. of Plasma Physics)</br>The analysis codes of neutronics, thermal-hydraulics and radioactivity and after-heat calculation are developed and briefly introduced. A multi-function blanket is studied. The analysis shows that the blanket can transmute almost...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18012023
The slab criticality problem for isotopic scattering with a backward leakTezcan, C.; Sever, R.; Yildiz, C. (Middle East Technical Univ., Ankara (Turkey))</br>In one-speed, time independent, neutron transport theory, an extremely anisotropic kernel consisting of a combination of backward and isotropic scattering is used to study the effect of backward scattering on the critical size in...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17061055
Localization of the spectrum and asymptotic behavior of the transport equationMokhtar-Kharroubi, M. (Paris-6 Univ., 75 (France). Lab. d'Analyse Numerique)</br>We localize the complex spectrum of the transport operator by means of an implicite curve in Lsup(p) setting, and an explicite one in L<sup>2</sup> setting. We give a direct approach to the asymptotic behaviour of the solution of...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21089068
Anisotropic scattering for integral transport codes: Pt. 1Roy, R. (Ecole Polytechnique, Montreal, PQ (Canada). Inst. de Genie Energetique)</br>The integral transport equation is solved in slab geometries in the case where anisotropic effects are taken into account. A model for anisotropic collision probability (CP) calculations based on an angle-dependent representation...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5100000
Argonne Code Center: benchmark problem book. Numerical determination of the space, time, angle, or energy distribution of particles in an assemblyArgonne National Lab., Ill. (USA)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22052465
Algorithms: optimal algorithm for the calculation of contributions to collision probabilities from a neutron pathWeiss, Z. (Buero fuer Angewandte Mathematik, Rodenbach (Germany, F.R.))</br>A fast algorithm for the calculation of contributions to first-flight collision probabilities is proposed. The algorithm is embodied into the subroutine COLPRO listed in the Appendix and can be used in 1D (slab) and general 2-D geometries....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:10455773
Orders-of-scattering solution of the Spencer--Lewis equationGarth, J.C. (RADC/ESR-Stop 30, Hanscom AFB, MA); Woolf, S.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9390681
Generalized rebalance: a common framework for transport acceleration methodsMiller, W.F. Jr. (Los Alamos Scientific Lab., NM)</br>Using slab geometry, generalized rebalance is presented as a class of iteration acceleration schemes applicable to the neutron transport equation. It is demonstrated that the diffusion-synthetic, variable-Eddington-factor, and conventional-rebalance...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11498626
Solution to the critical problem for the neutron transport equationBorysievicz, M. (Lab. di Ingegneria, Bologna, Italy)</br>The sufficient condition are formulated for the existence and uniqueness of the solution to the critical problem for the neutron transport equation. The conditions admit singular scattering kernels and black regions for certain neutron...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:30058748
Benchmarks on neutron leakage from iron and beryllium slabs and spheresBelousov, S.; Ilieva, K.; Popova, I.; Antonov, S. (INRNE, Sofia (Bulgaria))</br>Five benchmarks, recommended by the IAEA for nuclear power engineering have been calculated for assessment of Iron and Beryllium neutron data from the recent FENDL version. The FENDL multigroup data processed in IAEA by NJOY code...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22011254
Nature of complex time eigenvalues of the one speed transport equation in a homogeneous sphereDahl, E.B.; Sahni, D.C. (Chalmers Univ. of Tech., Goeteborg (Sweden). Dept. of Reactor Physics)</br>The complex time eigenvalues of the transport equation have been studied for one speed neutrons, scattered isotropically in a homogeneous sphere with vacuum boundary conditions. It is shown that the complex decay constants vary continuously...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26051462
Classification of the integral neutron transport operator and analysis of its spectral radiusJung, M. (Technische Universitaet Berlin (Germany))</br>The spectral radius of the integral neutron transport operator in unbounded regions is analyzed. A suitable integral operator in a bounded region is found, where previously found monotoneity and continuity results hold and a transitional...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21048580
Transfer by anisotropic scattering between subsets of the unit sphere of directions in linear transport theoryTrombetti, T. (Bologna Univ. (Italy). Lab. di Ingegneria Nucleare)</br>The exact kernel method is presented for linear transport problems with azimuth-dependent angular fluxes. It is based on the evaluation of average scattering densities (ASD's) that fully describe the neutron (or particle) transfer...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21004861
Comparisons of some neutron transport critical calculationsColombo, V.; Ravetto, P. (Dipartimento di Energetica, Politecnico di Torino, 10129 Torino (Italy))</br>Critical calculations can constitute a good test for the comparisons of the performances of numerical methods to solve the neutron transport equation for multiplying systems. For some paradigmatic calculations, physically significant...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14740273
The Asub(n) method and the spherical-harmonics approximation in neutron transport theoryCoppa, G.; Ravetto, P.; Sumini, M. (Politecnico di Torino (Italy))</br>The work presented in this paper completes the theoretical analysis that concerns the use of the Asub(n) approximate method in solving the monokinetic neutron transport equation. The method has been devised from the integral form...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26001744
A forward equation for stochastic neutron transportDegweker, S.B. (Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.)</br>A new formalism is developed for describing the stochastic neutron transport by the forward approach. This is used to derive a forward stochastic transport equation for this process. The first moment of this equation is the usual...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12610675
Point kinetics with ω-mode shape functions via multiple-time-scale asymptoticsDorning, J. (Univ. of Illinois, Urbana)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9356537
Functional analytic treatment of the transport equationGreenberg, W.; Zweifel, P.F. (Virginia Polytechnic Inst. and State Univ., Blacksburg)</br>A historical review of rigorous transport theory is presented. The original Larsen--Habetler work is reviewed and how the functional calculus is obtained in Lp spaces is described. Hangelbroek's approach to transport problems is outlined....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7250495
Two-half-space Milne problem in two-group neutron transport theoryIshiguro, Y.; Maiorino, R. (Cidade Univ., Sao Paulo, Brazil)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16079635
Low-discrepancy point sets in transport codesWarnock, T.T.</br>Los Alamos National Lab., NM (USA)</br>A drawback to Monte Carlo methods of computation is its rate of convergence. There are methods of sampling that have a better error estimate than those using random numbers. This paper gives the result of some preliminary experiments...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16014558
Monte Carlo calculations of the effective density factor (delta eigenvalue)Enosh, M.; Salmi, U.; Shalitin, D.; Wagschal, J.J.; Yeivin, Y. (Hebrew Univ., Jerusalem (Israel). Racah Inst. of Physics)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:6173311
Time-lethargy equivalence theorem in neutron transport theoryGanapol, B.D. (CEN de Saclay, Gif-sur-Yvette, France); Henninger, R.J.; Peddicord, K.L.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14726703
Error reduction techniques for Monte Carlo neutron transport calculationsJu, J.H.W.</br>Claremont Graduate School, CA (USA). Dept. of Mathematics</br>Monte Carlo methods have been widely applied to problems in nuclear physics, mathematical reliability, communication theory, and other areas. The work in this thesis is developed mainly with neutron transport applications in mind....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5150786
Approximation procedure for the neutron transport equation based on the use of surface harmonic tensorsKaper, H.G.; Leaf, G.K.; Lindeman, A.J.</br>Argonne National Lab., Ill. (USA)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26050490
Evaluation of higher K-eigenvalues of the neutron transport equation by S<sub>n</sub>-methodModak, R.S.; Sahni, D.C.; Paranjape, S.D. (Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.)</br>Many semi-analytical methods are being developed to evaluate higher eigenvalues of mono-energetic neutron transport equation. Here, a numerical approach is presented where the well known S<sub>n</sub>-method is used to generate higher...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:19025876
Some special properties of the neutron transport operator in bounded geometriesMokhtar-Kharroubi, M. (Universite de PARIS VI, Laboratoire d'Analyse Numerique 4, Place Jussieu, 75230-PARIS Cedex 05: France)</br>Existence and nonexistence eigenvalue results are given. We also estimate the leading eigenvalue of the transport operator in terms of some geometrical parameters of the configuration space. Some results related to the criticality...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21048582
Critical benchmarks in multigroup neutron transportCoppa, G.G.M.; Lapenta, G.; Ravetto, P. (Politecnico di Torino, Turin (Italy))</br>Space eigenfunction expansions are used within the multigroup neutron transport model in order to solve the criticality problem for homogeneous multiplying structures, without introducing any numerical space discretization. The solutions...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:10422658
Approximations to the neutron escape probability from an absorbing bodyChao, Y.A. (Carnegie-Mellon Univ., Pittsburgh); Martinez, A.S.</br>The mathematical problem of approximating the neutron escape probability function is studied through an analysis of the moment expansion of the function. The problem with possible divergence of the expansion is identified and avoided...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:46001708
Tracking strategies in 3D axial geometries for a MOC solverSciannandrone, D.; Santandrea, S. (CEA Saclay, DEN/DM2S/SERMA, 91191 Gif-sur-Yvette (France))</br>Web of Conferences, EDP Sciences, 17, Avenue du Hoggar, Parc d'Activite de Courtaboeuf, BP 112, F-91944 Les Ulis Cedex A (France)</br>The solution of the neutron transport equation in 3D domains is a high resource demanding task. One of the most successful method of solution of this equation is the Method of Characteristics (MOC). However, the huge number of trajectories...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:6214485
Computational complexity in multidimensional neutron transport theory calculations. Progress report, September 1, 1974--August 31, 1975Bareiss, E.H.</br>Northwestern Univ., Evanston, Ill. (USA)</br>The objectives of the research remain the same as outlined in the original proposal. They are in short as follows: Develop mathematically and computationally founded criteria for the design of highly efficient and reliable multi-dimensional...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13679296
Errata: approximate solutions to the half-space integral transport equation near a plane boundaryMilgrim, M.S. (Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:25062913
Variational derivation of multigroup P<sub>2</sub> equations and boundary conditions in planar geometryRulko, R.P. (Inst. de Genie Energetique, Ecole Polytechnique de Montreal, PQ (Canada))</br>We present a straightforward variational procedure based on a new physically motivated functional that leads from the multigroup planar geometry transport problem to the multigroup P<sub>2</sub> problem with clearly defined and rigorous...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15028453
Approximation procedures for the energy variable in neutronic distributionJachic, J. (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil))</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:27024101
Investigation of a continuum-amplitude taking into account non-diffusion effects in absence of discrete spectrum of the neutron transfer operator and comparison with experimentIsmatov, E.I.; Kenzhebaev, K.; Zhaldasova, S.M.; Khugaev, A.V.</br>AN RU, Tashkent (Uzbekistan). Inst. Yadernoj Fiziki</br>A study was made of a temporary behaviour of the neutron density N(t) and its damping velocity, λ(t). A calculation of the continuum-eigenvalue λ(t) and the continuum-amplitude K(λ) for various crystal mediums with taking into account...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11501421
Analysis of error in Monte Carlo transport calculationsBooth, T.E.</br>Los Alamos Scientific Lab., NM (USA)</br>The Monte Carlo method for neutron transport calculations suffers, in part, because of the inherent statistical errors associated with the method. Without an estimate of these errors in advance of the calculation, it is difficult...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9390675
Multiregion problems in plane geometry and the use of half-range orthogonality relationsIshiguro, Y. (Univ., Sao Paulo, Brazil)</br>A general systematic method to reduce multiregion problems in plane geometry to regular integral equations for the coefficients of singular-eigenfunction expansions is proposed. The method is based on the half-range orthogonality...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18039173
The compactness in neutron transport theoryMokhtar-Kharroubi, M. (Paris-VI Univ., 75 Paris (France). Laboratoire d'Analyse Numerique)</br>Under the assumption that the collision operator K is resolvent-compact relative to the absorption operator T, the spectrum of the transport operator A= T+K admits a discrete part. We give, here, necessary conditions and sufficient...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:23005498
Anisn codeSilva, C.F. da.</br>Published in summary form only
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9406306
User oriented numerical analysisWachspress, E.L.</br>Knolls Atomic Power Lab., Schenectady, N.Y. (USA)</br>Work typical of the numerical analyst is described. Emphasis is on problems encountered in modeling turbulent fluid flow and neutron diffusion. 1 figure
http://inis.iaea.org/Search/search.aspx?orig_q=RN:28075567
On the reciprocity-like relations in linear neutron transport theoryModak, R.S.; Sahni, D.C. (Bhabha Atomic Research Centre, Theoretical Physics Div., Bombay (India))</br>The existence of certain reciprocity-like relations in neutron transport theory was shown earlier under some quite restrictive conditions. Here, these relations are shown to be valid in more general situations by using a different...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16027117
Numerical resolution of the neutron transport equation by Octuplo-Po methodRibas, H.B.; Cunha Menezes Filho, A. da (Centro Tecnico Aeroespacial, Sao Jose dos Campos (Brazil))</br>The development of Octuplo-Po equations, from neutron transport equation, the numerical procedure for the solution of the equation, some validation tests and, some conclusions are presented. (E.G.)
http://inis.iaea.org/Search/search.aspx?orig_q=RN:4069909
Neutron transport for a slab with a degenerate scattering kernelLarson, H.A.; McCormick, N.J.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9372549
Compatible product angular quadrature for neutron transport in x-y geometryAbu-Shumays, I.K. (Bettis Atomic Power Lab., West Mifflin, PA)</br>The main features of this paper are the utilization of inherent two-dimensional symmetries and the development of accurate angular quadrature coordinates and weights especially suited for the net and/or partial currents and all the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8347575
Transport effects on nodal coupling parametersMenezes, A.D.; Chan, G.; Ancona, A.; Becker, M.; Harris, D.R. (Rensselaer Polytechnic Inst., Troy, NY)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18049814
On a nonlinear neutron transport equationPachpatte, B.G. (Maulana Azad Coll., Calcutta (India). Dept. of Mathematics)</br>In this paper, the existence and uniqueness of the solutions of a certain nonlinear time-independent neutron transport equation is studied. The approach is based on converting this equation into an equivalent integral equation using...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18092638
Spectral theory of the neutron transport operator in bounded geometriesMokhtar-Kharroubi, M. (Universite de Paris 6, Laboratoire d'Analyse Numerique 4, place Jussieu, 75230 Paris Cedex 05, France)</br>We give a complete description of the real point spectrum of the transport operator for positive collision operators: necessary and sufficient conditions for existence; necessary and sufficient conditions for finiteness; estimates...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:50054775
Conjugacy Analysis of the Finite-Difference Equations of the Method of Characteristics on the Basis of a Linear-Algebraic FormulationSuslov, I. R.; Tormyshev, I. V. (State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI) (Russian Federation))</br>A linear-algebraic form of the equations of the method of characteristics, which is used to approximate the neutron transport equation, is obtained. It is shown on the basis of the obtained linear-algebraic form that the discrete...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8342381
Inverse problem for multigroup neutron transport theorySiewert, C.E. (North Carolina State Univ., Raleigh); Oezisik, M.N.; Yener, Y.</br>The inverse problem for multigroup transport theory is solved for the cases of plane and spherical symmetry
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21009196
Approximations for very-high-order eigenvalues in neutron transport theoryGaris, N.S.; Sjoestrand, N.G. (Chalmers Univ. of Tech., Goeteborg (Sweden). Dept. of Reactor Physics)</br>Some regularities are pointed out in the spectrum of criticality eigenvalues for homogeneous spheres and infinite slabs with neutrons of one speed. Using a hypothesis of van de Hulst and Stark, some formulae are derived for the high-order...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:27002943
Classical and notsoclassical analysisMilgram, M. (Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.)</br>Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs</br>Short communication. 4 refs
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12583579
Interpretation of conditional Monte Carlo as a form of importance samplingDubi, A.; Horowitz, Y.S. (Ben Gurion University of the Negev, Beersheva, Israel)</br>Conditional Monte Carlo has been recognized as a potentially useful method in various Monte Carlo applications. It seems, however, that the method has not gained widespread popularity, presumably due to the complexity involved in...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13676941
A solution of the multigroup transport equation using a weighted residual techniqueFletcher, J.K. (UKAEA Risley Nuclear Power Development Establishment)</br>A solution of the multigroup diffusion equation using a weighted residual technique is described. The implementation enables high-order polynomial approximations to be made to the flux. The neutron transport equation is solved by...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14744887
On linear extrapolation distances, extrapolated endpoints, and eigenvaluesRahnema, F.; Pomraning, G.C. (Univ of Calif, Los Angeles, USA)</br>It is well known that for a large reactor a diffusion calculation of the system eigenvalue (criticality) is weakly dependent on the linear extrapolation distance /gamma/. This weak dependence is characterized by a smallness parameter...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17005467
Alternative formulation of the monokinetic transport equationCoppa, G.; Ravetto, P.; Sumini, M. (Politecnico di Torino, Dipartimento di Energetica, Corso Duca degli Abruzzi, 24 10129 Torino, Italy)</br>After recalling a technique already exploited in stationary neutron transport, the dynamic linear monokinetic equation for general geometry is cast into an integro-differential form where a second order space Laplace operator and...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:4080193
Correction for higher-order scattering anisotropy in neutron transport theoryStacey, W.M. (Argonne National Lab., Ill. (USA))</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22049433
Time-eigenvalues of the one-speed neutron transport equation in two-medium slabs and spheresGaris, N.S.</br>Chalmers Univ. of Tech., Goeteborg (Sweden). Dept. of Reactor Physics</br>The transport of monoenergetic neutrons with isotropic scattering and vacuum boundary conditions is studied in two-medium spherical and plane systems. The mean-free-path is assumed to be the same in the two media. The two coupled...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21017359
Neutron transport theory in a ring reactorWilliams, M.M.R. (Michigan Univ., Ann Arbor, MI (USA). Dept. of Nuclear Engineering)</br>The one-speed transport equation is solved for a ring reactor. A complete solution is obtained for the space-time relaxation of a pulse of neutrons in a multiplying medium in which delayed neutrons are neglected. The solution consists...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26044962
Study on non-minimum phase reactor systemLee Baoyan (Qinghua Univ., Beijing, BJ (China)); Luo Zhengpei (Qinghua Univ., Beijing, BJ (China))</br>The traditional reactor noise analysis methods assumed that the input of a reactor model is a Gaussian white noise and a reactor system is a minimum-phase system. The authors have checked the probability density distribution of the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22049435
Invariance relations for bilinear functionals in the evaluation of the anisotropic scattering sourceBorsari, R.; Trombetti, T. (Bologna Univ. (Italy). Lab. di Ingegneria Nucleare); Lewins, J.D. (Cambridge Univ. (UK). Dept. of Engineering)</br>We derive invariance properties for bilinear functionals defined as integrals of the angular source density due to anisotropic scattering transfer from an origin to a destination subset of the unit sphere of directions. The integrand...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:23045719
Variational nodal transport solutions of multigroup criticality problemsCarrico, C.B.; Lewis, E.E. (Northwestern Univ., Evanston, IL (United States). Dept. of Mechanical Engineering)</br>Variational nodal methods are extended to treat multigroup and criticality problems and are implemented as a module for the production code DIF3D at Argonne National Laboratory. New within-group solution algorithms based on the partitioning...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5108679
Application of the probability table method to Monte Carlo temperature difference calculationsPrael, R.E.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8345660
Finite element methods for radiation transport calculationsLewis, E.E. (Northwestern Univ., Evanston, IL)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9390674
Neutron spectra associated with a fast pulse assemblyHarvey, J.T.</br>Arkansas Univ., Little Rock (USA)</br>Neutron spectra have been measured by the threshold foil activation technique for the White Sands Missile Range Fast Burst Reactor. The neutron spectra for free-field, free-field with the experimenters table in place, for the in-core...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14782069
On confidence limits and statistical convergence of Monte Carlo point-flux estimators with unbounded varianceDubi, A.; Elperin, T. (Ben-Gurion Univ. of the Negev, Beersheba (Israel). Dept. of Nuclear Engineering); Rief, H. (Commission of the European Communities, Ispra (Italy). Joint Research Centre)</br>The problem of analyzing the statistical error of Monte Carlo point-flux estimators with unbounded variance is considered. The results are based on the generalization of the classical limit theorem for summands of identically-distributed...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:43031240
Analysis of an a posteriori error estimator for the transport equation with S<sub>N</sub> and discontinuous Galerkin discretizationsFournier, D. (CEA, DEN, DER/SPRC/LEPh, Cadarache, F-13108 Saint Paul-lez-Durance (France)); Le Tellier, R.; Suteau, C. (CEA, DEN, DER/SPRC/LEPh, Cadarache, F-13108 Saint Paul-lez-Durance (France)), E-mail: damien.fournier@cea.fr</br>We present an error estimator for the S<sub>N</sub> neutron transport equation discretized with an arbitrary high-order discontinuous Galerkin method. As a starting point, the estimator is obtained for conforming Cartesian meshes...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48094897
Fractional neutron transport in finite clumpy reactors with high-order scatteringSallah, M. (Institute for Nuclear Research Physics Department, Faculty of Science, Mansoura University, Mansoura P.O. Box 35516, (Egypt)), E-mail: msallahd@mans.edu.eg</br>The nuclear reactor dynamics are studied using fractional neutron kinetics equations by investigating the space-fractional neutron transport through a clumpy reactor. The fractional differential operator is taken in terms of the Riemann-Liouville...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13678353
Status of integral transport theoryKavenoky, A.</br>CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Physique des Particules Elementaires</br>The integral transport theory has been first applied to one-dimensional problems: these treatments are presented with their most recent developments involving polynomial expansions and anisotropic scattering. Nowadays the more important...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8293724
Study on one determinant roots in multigroup transport theoryAbramov, B.D.</br>Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst.</br>The properties of the roots of a functional that appears in an analytical solution of a coupled one-speed (group) neutron transport equation are investigated. The problems of the number of roots, their parity, possible place in the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:38027917
Problems in the neutron dynamics of source-driven systemsRavetto, P. (Politecnico di Torino, Dipartimento di Energetica, Turin (Italy)), E-mail: ravetto@polito.it</br>The present paper presents some neutronic features of source-driven neutron multiplying systems, with special regards to dynamics, discussing the validity and limitations of classical methods, developed for systems in the vicinity...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:29027930
A higher order nodal diffusion method for spatial kinetics calculationsTomasevic, Dj. (Atomic Energy Corp. of South Africa Ltd., Pretoria (South Africa)); Zivanovic, R. (Technikon Pretoria (South Africa))</br>A major advance in the treatment of spatial variables in global reactor calculations has been the development of the transverse integrated nodal methods. A consistent quasi-one-dimensional nodal method have been formulated recently...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22018139
Hybrid variational principles and synthesis method for finite element neutron transport calculationsAckroyd, R.T. (Queen Mary Coll., London (UK). Dept. of Nuclear Engineering); Nanneh, M.M. (Imperial Coll. of Science and Technology, London (UK). Dept. of Mechanical Engineering)</br>A family of hybrid variational principles is derived using a generalised least squares method. Neutron conservation is automatically satisfied for the hybrid principles employing two trial functions. No interfaces or reflection conditions...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:4080129
Multidirectional modal representation for neutron transport analysisHarms, A.A.; Kushneriuk, S.A.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:6208289
Integral transport for 2-D benchmark, shielding problemsLoyalka, S.K.; Tsai, R.W. (Univ. of Missouri, Columbia)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:23037841
The F<sub>N</sub> method for a specified isotropic scattering modelYildiz, C. (Istanbul Univ. (Turkey))</br>The variation of the critical slab thickness in monoenergetic neutron transport theory is studied. The F<sub>N</sub> method is used to solve, for the case of specified isotropic scattering, the critical problem. The results obtained...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:27049247
(Weakly) three-dimensional caseologyPomraning, G.C. (California Univ., Los Angeles, CA (United States). School of Engineering and Applied Science)</br>The singular eigenfunction technique of Case for solving one-dimensional planar symmetry linear transport problems is extended to a restricted class of three-dimensional problems. This class involves planar geometry, but with forcing...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13708662
Solution of the transport equation in a critical periodic plane reactor latticeKheilova, M. (Vysoke Uceni Technicke, Brno (Czechoslovakia). Elektrotechnicka Fakulta)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9416208
Complex trial functions in the even-parity transport equationBlomquist, R.N.; Lewis, E.E. (Northwestern Univ., Evanston, IL)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15016240
On angular flux computations in neutron-transport theoryGarcia, R.D.M.; Siewert, C.E. (North Carolina State University, Nuclear Engineering Department Raleigh, North Carolina 27650)</br>The use of the F /SUB N/ method for computing angular fluxes in neutron-transport theory is reviewed, and accurate results for a basic problem are reported
http://inis.iaea.org/Search/search.aspx?orig_q=RN:25035396
Eigenvalues for reflecting boundary conditions in one-speed neutron transport theoryGaris, N.S.; Sjoestrand, N.G. (Chalmers Univ. of Technology, Goeteborg (Sweden). Dept. of Reactor Physics)</br>The spectrum of criticality eigenvalues for the one-speed neutron transport equation has been studied for an infinite slab with reflexion coefficients R<sub>1</sub> and R<sub>2</sub> at the surfaces. For R<sub>1</sub> = R<sub>2</sub>...