INIS Repository Search - Results for the query - DEC:"TRANSPORT"
http://inis.iaea.org/Search/search.aspx?orig_q=DEC%3a%22TRANSPORT%22&searchFor=Feed&sort=date:D:L:d1&search-option=Everywhere
Below are the best match search results for the above query from INIS Repository Searchen-US
http://inis.iaea.org/Search/search.aspx?orig_q=RN:33022156
Environmental impacts of public transport. Why peak-period travellers cause a greater environmental burden than off-peak travellersRietveld, P. (Vrije Universiteit, msterdam (Netherlands))</br>Given the difference between peak and off-peak occupancy rates in public transport, emissions per traveller kilometre are lower in the peak than in the off-peak period, whereas the opposite pattern is observed for cars. It is argued...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:32009526
Helping transit grow: the levy storyHeald, C.</br>Arguments for and against the highly controversial levy approved by Translink, the transportation authority in Greater Vancouver, are discussed. This highly controversial plan will cost car owners in the Greater Vancouver Regional...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8306936
Variational coarse-mesh transport method based on constrained angular trial functionsBriggs, L.L.; Lewis, E.E. (Northwestern Univ., Evanston, IL)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21012929
Infinite slab-shield dose calculationsRussell, G.J.</br>Los Alamos National Lab., NM (USA)</br>I calculated neutron and gamma-ray equivalent doses leaking through a variety of infinite (laminate) slab-shields. In the shield computations, I used, as the incident neutron spectrum, the leakage spectrum (<20 MeV) calculated for...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16033015
Finite element method for solving neutron transport problemsFerguson, J.M.; Greenbaum, A.</br>Lawrence Livermore National Lab., CA (USA)</br>A finite element method is introduced for solving the neutron transport equations. Our method falls into the category of Petrov-Galerkin solution, since the trial space differs from the test space. The close relationship between this...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48083591
Wielandt iteration combined with multi-group GMRES for accelerating matrix MOC convergenceWu Wenbin (Department of Engineering Physics, Tsinghua University, Beijing (China); Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)); Li Qing (Science and Technology...</br>In the Matrix MOC a linear algebraic equation system can be constructed by sweeping only once, and then solving the linear system takes the place of repeatedly characteristics sweeping. Traditionally, k_e_f_f is computed by power...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14744884
Multigroup transport theory - 2. numerical resultsGarcia, R.D.M.; Siewert, C.E. (NC State Univ, Raleigh, USA)</br>The F/sub N/ method is used to establish particularly accurate solutions, at modest cost, for the emerging angular fluxes basic to a class of multigroup particle-transport problems. A study of the fundamental computational aspects...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16056467
Explicit expressions for the moments of the monoenergetic neutron-transport equation for isotropic scattering in an infinite plane mediumGanapol, B.D. (Arizona Univ., Tucson (USA). Dept. of Nuclear and Energy Engineering)</br>The analytical determination of the spatial and angular moments of the monoenergetic neutron-transport equation in an infinite medium initiated by Case, de Hoffmann and Placzek 30 years ago is completed. Analytical expressions for...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13711351
Choice of angular current approximations for solving neutron transport problems in 2-D by interface current approachMohanakrishnan, P. (Bhabha Atomic Research Centre, Bombay (India). Theoretical Reactor Physics Section)</br>A computer programme, RICANT, for the solution of 2-D neutron transport problems is described. This uses the interface current approach, where the angular neutron currents crossing region surfaces are expanded in terms of associated...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7250544
Method for processing ENDF/B photon form factor dataLucius, J.L.; Greene, N.M. (Oak Ridge National Lab., TN)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:20045841
A new application of space asymptotic transport theoryColombo, V.; Corno, S.E.; Ravetto, P. (Politecnico di Torino (Italy))</br>The present paper concerns a proper statement and a new application of the so-called space asymptotic neutron transport theory in stationary reactor physics. In the first part we formulate the essential assumptions of space asymptotic...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17030520
Energy dependent neutron transport in multi-dimensional systemsNagy, M.E.; El-Guebaly, L.A.; Wassef, W.A.; Sawan, M.E. (Reactor Department, Nuclear Research Centre, A.E.E., Cairo, Egypt)</br>The kernel factorization method used to solve the steady state one speed integral transport equation in a rectangular parallelepiped is used to solve the energy dependent problem. A model is developed to solve the multigroup k eigenvalue...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:22063607
An analytical benchmark solution to the time-dependent multigroup neutron transport equationGanapol, B.D. (Arizona Univ. Tucson, AZ (USA). Dept. of Nuclear and Energy Engineering)</br>Benchmark quality results for the time-dependent multigroup neutron transport equation are presented. These results represent a significant breakthrough in analytical benchmarking
http://inis.iaea.org/Search/search.aspx?orig_q=RN:33034651
P<sub>N</sub> solutions of the time-dependent neutron transport equation with anisotropic scattering in a homogeneous sphereYildiz, Cemal (Department of Physics, Istanbul Technical University, Maslak, Istanbul (Turkey))</br>In an earlier paper, the spherical harmonics method for the solution of the time-dependent transport equation with the Marshak boundary conditions was presented in order to investigate the effect of a strongly anisotropic scattering...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17011624
The energy-dependent backward-forward-isotropic scattering model with some applications to the neutron transport equationWilliams, M.M.R. (Queen Mary Coll., London (UK). Dept. of Nuclear Engineering)</br>A multigroup formalism is developed for the backward-forward-isotropic scattering model of neutron transport. Some exact solutions are obtained in two-group theory for slab and spherical geometry. The results are useful for benchmark...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17042459
Analytical solutions to the moment transport equations II Multiregion, multigroup, 1-D slab, cylinder and sphere criticality and source problemsLee, C.E. (Technadyne, Albuquerque, NM (USA)); Fan, W.C.P. (Texas A and M Univ., College Station (USA). Dept. of Nuclear Engineering); Dias, M.P. (Moratuwa Univ. (Sri Lanka). Dept. of Electrical Engineering)</br>Analytical multigroup multiregion Psub(N) criticality solutions are obtained for 1-D slabs, cylinders and spheres. A two-group two-/three-region slab with reflective boundary conditions, a one-group linear anisotropic cylinder with...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7250490
Fictitious scattering multigroup cross sectionsCramer, S.N.; Engle, W.W. Jr. (Oak Ridge National Lab., TN)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8306958
Local separation of angle and energy in one-dimensional transportRakavy, G.; Tikochinsky, Y.; Wagschal, J.J. (Hebrew Univ., Jerusalem)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16048638
Principles of electromagnetic radiation interaction with matterTso Ching Ping (Malaya Univ., Kuala Lumpur (Malaysia). Faculty of Engineering)</br>In the use of nuclear techniques, one of the safety problems is the protection of personnel and delicate instruments against harmful radiation. It is therefore of prime importance that the designer of nuclear experiments have a basic...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8320293
Diffusion synthetic acceleration methods for the diamond-differenced discrete-ordinates equationsAlcouffe, R.E.</br>Los Alamos Scientific Lab., N.Mex. (USA)</br>A class of acceleration schemes is investigated which resembles the conventional synthetic method in that they utilize the diffusion operator in the transport iteration schemes. The accelerated iteration involves alternate diffusion...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48028791
Application of a numerical transport correction in diffusion calculationsTomatis, Daniele; Dall'Osso, Aldo (AREVA NP, Paris La Defense Cedex (France)), E-mail: daniele.tomatis@areva.com, E-mail: aldo.dallosso@areva.com</br>Full core calculations by ordinary transport methods can demand considerable computational time, hardly acceptable in the industrial work frame. However, the trend of next generation nuclear cores goes toward more heterogeneous systems,...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:46008117
On the stability of the Discrete Generalized Multigroup methodGibson, Nathan A.; Forget, Benoit, E-mail: ngibson@mit.edu</br>Highlights: • Picard iteration with Discrete Generalized Multigroup found to be unstable in general. • Krasnoselskij (relaxation) iteration scheme yields improved stability. • Informed choice of group map improves convergence behavior....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:38015823
Improvement of the efficiency of two-dimensional multigroup transport calculations assuming isotropic reflection with multilevel spatial discretizationStankovski, Z.; Zmijarevic, I. (DEMT-SERMA, CEN Saclay (France))</br>This paper presents two approximations used in multigroup two-dimensional transport calculations in large, very homogeneous media: isotropic reflection together with recently proposed group-dependent spatial representations. These...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11500160
Investigation of new estimation approaches for nuclear reactor computations by Monte CarloRagheb, M.M.H.</br>Wisconsin Univ., Madison (USA)</br>New estimation approaches for nuclear reactor calculations by Monte Carlo are developed and investigated, with the purpose of surmounting or alleviating existing difficulties facing the application of the Monte Carlo Method. Bias-free...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8294792
Monte Carlo nonuniform sampling technique applied to the Klein-Nishina probability density functionHorowitz, Y.S.; Mordechai, S. (Ben Gurion Univ. of the Negev, Beersheva, Israel)</br>The Monte Carlo generalized rejection technique provides a continuous passage from the inverse equation sampling method to the uniform sampling rejection method; it is well known that the nonuniform rejection method can be used to...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:19091101
Discrete ordinates scheme for quadrilateral meshesKumar, V.; Menon, S.V.G. (Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.)</br>A simple extension of the discrete ordinates method for solving the transport equation with quadrilateral meshes in X-Y and R-Z geometry is described. Numerical results of some benchmark problems are presented for showing the adequacy...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16056471
The albedo problem in the case of multiple synthetic scattering taking place in a plane-symmetric slabShafiq, A.; Meyer, H.E. de; Grosjean, C.C. (Ghent Rijksuniversiteit (Belgium). Seminarie voor Wiskundige Natuurkunde)</br>An approximate model based on an improved diffusion-type theory is established for treating multiple synthetic scattering in a homogeneous slab of finite thickness. As in the case of the exact treatment given in the preceding paper...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17089238
Computational methods of neutron transportLewis, E.E.; Miller, W.F.</br>This books presents a balanced overview of the major methods currently available for obtaining numerical solutions in neutron and gamma ray transport. It focuses on methods particularly suited to the complex problems encountered in...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12603830
Angular current approximations in neutron transport calculations using interface currentsMohanakrishnan, P. (Bhabha Atomic Research Centre, Bombay (India). Theoretical Reactor Physics Section)</br>It has been recognized recently that accurate numerical solutions of the neutron transport equation in two dimensions can be obtained by interface current approach provided the angular dependence of these currents is properly accounted...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:34039538
Revised interface-current relations for the unit-cell transport problem in cylindrical and spherical geometriesLeite, S.Q. Bogado</br>Escape and transmission probabilities, defined in terms of both the region the neutron originates from and the region it penetrates, are used to develop new interface-current relations for unit-cells with an arbitrary number of annular...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:39111409
Chebyshev polynomial (T<sub>N</sub>) approximation to neutron transport theory and application to the critical slab problemBuelbuel, A.; Anli, F. (Kahramanmaras Suetcue Imam Univ. (Turkey). Dept. of Physics)</br>The critical slab problem has been studied in the one-speed neutron transport equation with isotropic scattering by using the first kind of Chebyshev Polynomials. The moment criticality solutions were obtained for the uniform finite...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26027524
Numerical method for multigroup one-dimensional S<sub>N</sub> eigenvalue problems with no spatial truncation errorAbreu, M.P.; Filho, H.A. (COPPE/UFRJ-Nuclear, Rio de Janeiro (Brazil)); Barros, R.C. (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil))</br>The authors describe a new nodal method for multigroup slab-geometry discrete ordinates S<sub>N</sub> eigenvalue problems that is completely free from all spatial truncation errors. The unknowns in the method are the node-edge angular...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:10449423
Application of the symmetric SOR and the symmetric SIP methods for the numerical solution of the neutron diffusion equationWang, H.H. (IBM Corp., Palo Alto, CA)</br>The symmetric successive overrelaxation (SSOR) method and the symmetric strongly implicit procedure (SSIP) method are applied to a number of two-dimensional elliptic partial differential equations typical of those encountered in reactor...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:19078348
A perturbation theory for the non-linear system of neutron transport and burnup equationsAlp, C. (Istanbul Technical Univ. (Turkey). Inst. for Nuclear Energy)</br>A perturbation theory for use in nuclear reactor burnup analysis is derived. An important characteristic function is defined, and the related adjoint equation is obtained simply by using the variational principle. The adjoint matrix...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15045688
Synthetic acceleration scheme for radiative diffusion calculationsMorel, J.E.; Larsen, E.W.; Matzen, M.K.</br>Sandia National Labs., Albuquerque, NM (USA); Los Alamos National Lab., NM (USA)</br>A synthetic method has been developed to accelerate the iterative convergence of the multigroup radiative diffusion equations with temporally implicit material-radiation coupling. The performance of the method is characterized by...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:35088059
New development of the three-dimensional characteristics solver MCI in DRAGONWu, G.J.; Roy, R. (Inst. de genie nucleaire, Ecole Polytechnique de Montreal, Montreal, Quebec (Canada))</br>In this paper, we present the recent development of our 3D characteristics solver MCI. The Self-Collision Rebalancing (SCR) technique uses the self-collision probabilities to reduce the total iteration number. The proof of equivalence...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5108635
Ambiguity in the definition of effective diffusion coefficients in slab latticesGelbard, E.M.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11554176
Escape and transmission probabilities in cylindrical geometryBjerke, M.A.</br>Oak Ridge National Lab., TN (USA)</br>An improved technique for the generation of escape and transmission probabilities in cylindrical geometry was applied to the existing resonance cross section processing code ROLAIDS. The algorithm of Hwang and Toppel, [ANL-FRA-TM-118]...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11534011
Comparison of photon-production processing codes LAPHNGAS, MACK-IV, and NJOYBarrett, R.J.; Ford, W.E. III; Gohar, Y.; Bohn, T.S.; MacFarlane, R.E.; Boicourt, R.M.</br>Los Alamos Scientific Lab., NM (USA)</br>Several laboratories have independently developed computer codes that use evaluated data from the ENDF/B file to produce group-averaged cross sections and transfer matrices for neutron-induced photon production. There have been several...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12603866
Linear characteristic method for spatially discretizing the discrete ordinates equations in (X,Y)-geometryLarsen, E.W.; Alcouffe, R.E.</br>Los Alamos Scientific Lab., NM (USA)</br>A new linear characteristic (LC) spatial differencing scheme for the discrete-ordinates equations in (x,y) geometry is described, and numerical comparisons are given with the diamond difference (DD) method. The LC method is more stable...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18063720
The criticality problems with the Fsub(N) method for the FBIS modelTezcan, C. (Maden Tetkik ve Arama Enstitusu, Ankara (Turkey)); Yildiz, C. (Istanbul Technical Univ., (Turkey). Dept. of Physics)</br>In one-speed, time-independent, neutron transport theory, the Fsub(N) method is used for the FBIS (forward-backward-isotropic scattering) model to reinvestigate the behaviour of the critical size in plane and spherical geometries....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:13711333
An approximate method for the calculation of transmission probabilities through hollow cylindersGilai, D. (Israel Atomic Energy Commission, Beersheba. Nuclear Research Center-Negev)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:41058939
Complex system simulation through agent based modelling: pedestrian flows in underground stationsPannicelli, A. (Dipartimento Tecnologie per l'Energia, le Fonti Rinnovabili e il Risparmio Energetico, ENEA, Rome (Italy)); Liberto, C. (Consorzio TRAIN, Rome (Italy))</br>Investigating and modelling pedestrian flows in underground stations is essential to improve criteria in stations designing and in order to manage ordinary and critical situations, simulating the human behaviour in such situations.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:45033690
New technique to reformat multigroup cross-sections for Monte-Carlo calculationSuslov, L. R.; Tormyshev, I. V.; Mel'nikov, K. G. (FSUE SSCRF-IPPE, Bondarenko sq. 1, 249033, Obninsk, Kaluga district (Russian Federation))</br>New method to calculate equi-probability bins from Legendre expansion scattering cross-sections is proposed. The method uses correction of equi-probability bins boundaries to provide conservation of the first angular moment. CRSRD-ST...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:26046084
Plasma transport as a dissipative structureUehara, K. (Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment)</br>The physical basis for transport analysis of magnetized plasma has for a long time been based on two body collisional diffusion theory, including neo-classical and quasi-linear theory. In the former, it is mainly considered that charged...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:8306948
State-space splitting in Monte Carlo calculationsMacdonald, J.L.; Cashwell, E.D. (Los Alamos Scientific Lab., NM)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17051519
Variational methods in steady state diffusion problemsLee, C.E.; Fan, W.C.P.; Bratton, R.L. (Dept. of Nuclear Eng., Texas A and M Univ., College Station, TX 77843)</br>Classical variational techniques are used to obtain accurate solutions to the multigroup multiregion one dimensional steady state neutron diffusion equation. Analytic solutions are constructed for benchmark verification. Functionals...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:42010546
Adjoint Monte Carlo neutron transport using cross-section probability table representationDiop, Cheikh M'Backe (Service d'Etudes des Reacteurs et de Mathematiques Appliquees, Direction de l'Energie Nucleaire, Commissariat a l'Energie Atomique, CEA/Saclay, 91191 Gif-sur-Yvette (France)); Petit, Odile; Jouanne, Cedric; Coste-Delclaux,...</br>The probability table representation of cross-sections is generally used to deal with neutron interactions in the unresolved energy range. In the frame of neutron transport methods, the capability of the probability table representation...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:28032418
A generic method of analytical solution for approximations of the linear transport equationCardona, Augusto V.</br>Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Escola de Engenharia</br>In this work it is presented a generic method of analytical solution to the one-dimensional S<sub>N</sub>, P<sub>N</sub>, W<sub>N</sub>, Ch<sub>N</sub>, A<sub>N</sub> and L D<sub>N</sub> approximations of the linear transport equation....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:10443574
Singularities of the solution to the neutron transport equation in cylindrical symmetryKulikowska, T. (Institute of Nuclear Research, Warsaw (Poland))</br>The singularities of the solution to the neutron transport equation for systems with cylindrical symmetry are discussed in detail. It is shown that the case of spherical symmetry can be considered as a special case of cylindrical...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:24033472
Treatment of the reflector in two-group diffusion calculations for LWRsBernnat, W. (Stuttgart Univ. (Germany). Inst. fuer Kernenergetik und Energiesysteme)</br>A general method for the treatment of radial or axial reflectors in diffusion calculations for light water reactors will be described. The method is based on pre-calculated response matrices for the reflector via external boundary...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:28079205
Advances in the development of a subgroup method for the self-shielding of resonant isotopes in arbitrary geometriesHebert, A. (Commissariat a l'Energie Atomique, Gif-sur-Yvette (France). Centre d'Etudes de Saclay)</br>The subgroup method is used to compute self-shielded cross sections defined over coarse energy groups in the resolved energy domain. The validity of the subgroup approach was extended beyond the unresolved energy domain by partially...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:37070499
On the relation between neoclassical transport and turbulent transportShaing, K.C. (Engineering Physics Department, University of Wisconsin, Madison, Wisconsin 53706 (United States))</br>It is demonstrated through the flux-force relationship in the neoclassical theory that when neoclassical transport fluxes are improved, the damping rate of the radial electric field of the zonal flow is reduced. This, in turn, leads...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:42004331
FPGA hardware acceleration for high performance neutron transport computation based on agent methodology - 318Shanjie, Xiao; Tatjana, Jevremovic (Utah Nuclear Engineering Program, The University of Utah, Salt Lake City, UT (United States))</br>American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)</br>The accurate, detailed and 3D neutron transport analysis for Gen-IV reactors is still time-consuming regardless of advanced computational hardware available in developed countries. This paper introduces a new concept in addressing...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9410172
ETOE-2/MC<sup>2</sup>-2/SDX multigroup cross-section processingToppel, B.J.; Henryson, H. II; Stenberg, C.G.</br>Argonne National Lab., Ill. (USA)</br>The ETOE-2/MC<sup>2</sup>-2/SDX multigroup cross-section processing codes were designed to provide a comprehensive neutron cross-section processing capability for a wide range of applications including critical experiment analysis...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:6207050
Users manual for TDT (time-dependent TASK)Tomlinson, E.T.; Dodds, H.L.; Lillie, R.A.; Robinson, J.C.</br>Oak Ridge National Lab., Tenn. (USA)</br>TDT is written in FORTRAN-IV, using flexible dimensioning, and is designed for computers in the IBM-360 series. TDT solves the one-dimensional multigroup form of the time-dependent reactor kinetics equations, allowing an arbitrary...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48095188
Electronic Toll Collection Systems and their Interoperability: The State of ArtHeras Molina, J. de la; Gomez Sanchez, J.; Vassallo Magro, J.M.</br>The European Electronic Toll Service (EETS) was created in 2004 with the aim of ensuring interoperability among the existing electronic toll collection (ETC) systems in Europe. However, the lack of cooperation between groups of stakeholders...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18037272
Two part carriage for rail transport of heavy components in nuclear power stationsCharvat, Z.; Soucek, K.; Tennie, M.</br>Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)</br>Each part of the carriage for fuel element transport containers has two supporting blocks opposite each other in the longitudinal direction. These are freely adjustable in the longitudinal direction. Both parts of the carriage are...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21058800
Reliability on the move: safety and reliability in transportationGuy, G.B. (ed.) (British Nuclear Fuels plc, Risley (UK); Safety and Reliability Society, Manchester (UK))</br>Safety and Reliability Society, Manchester (UK)</br>The development of transportation has been a significant factor in the development of civilisation as a whole. Our technical ability to move people and goods now seems virtually limitless when one considers for example the achievements...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48095158
Alternate Double Single Track LinesMoraga Contreras, P.; Grande Andrade, Z.; Castillo Ron, E.</br>The paper discusses the advantages and shortcomings of alternate double single track (ADST) lines with respect to double track lines for high speed lines. ADST lines consists of sequences of double and single track segments optimally...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11564025
An existence and uniqueness theorem for generalized birth and death processesCapasso, V. (Bari Univ. (Italy)); Paveri-Fontana, S.L. (State Univ. of New York, Buffalo (USA))</br>A generalized version of the continuous-time birth-and-death stochastic model is formulated. Employing semigroup methods, it is shown that the initial value problem subject to appropriate regularity requirements admits a unique solution...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:17011623
Special eigenvalues of the time-dependent one-speed neutron-transport equation for a homogeneous sphere with anisotropic scatteringDahl, E.B. (Chalmers Univ. of Tech., Goeteborg (Sweden). Dept. of Reactor Physics)</br>The time dependence of a neutron population in a homogeneous sphere has been studied. The neutrons are of one speed and are assumed to be scattered with linear anisotropy. Vacuum boundary conditions are used. It is shown that the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:33018557
Parallel acceleration and rebalancing schemes for solving transport problems using PVMQaddouri, A. (Inst. de Genie Nucleaire, Ecole Polytechnique de Montreal, Montreal, Quebec (Canada); Centre de Recherches Mathematiques, Univ. de Montreal, Montreal, Quebec (Canada)); Roy, R. (Inst. de Genie Nucleaire, Ecole Polytechnique...</br>In this paper, parallelization for CP calculation and multigroup flux computation are presented. Implementation of acceleration and neutron rebalancing strategies is also investigated. Particular techniques pertinent to the two-step...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12598326
Monte Carlo perturbation theory in neutron transport calculationsHall, M.C.G. (Imperial Coll. of Science and Technology, London, England)</br>The need to obtain sensitivities in complicated geometrical configurations has resulted in the development of Monte Carlo sensitivity estimation. A new method has been developed to calculate energy-dependent sensitivities of any number...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12594263
Anisotropic transport techniques and associated neutron transfer cross-section evaluationHong, K.J.</br>Kansas State Univ., Manhattan (USA)</br>Several computational techniques for treating highly anisotropic transport problems are investigated. A detailed analysis of the neutron scattering process indicates that the multigroup transfer cross sections typically have very...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:5108671
Calculation of multigroup cross sections and transfer matrices for target nuclei with arbitrary velocity distributionsHarris, D.R.; Wallace, J.M.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:21083670
Minimum fuel loadingPoon, P.W.; Lewins, J.D. (Cambridge Univ. (UK). Dept. of Engineering)</br>The minimum fuel loading for a homogeneous reactor is found using calculus of variations for one-group and multi-group diffusion theory (Goertzel's minimum critical mass theorem). Some extensions are given and the results are compared....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:49082851
Use of 3-D neutron-gamma transport code ATES3 for radiation shielding analysisGupta, Anurag (Reactor Physics Design Division, Bhabha Atomic Research Centre, Mumbai (India)); Modak, R.S., E-mail: anurag@barc.gov.in</br>The 3-D steady-state S<sub>N</sub> neutron-gamma transport theory code ATES3 developed at BARC can be utilized for external source problems such as shielding analysis. A brief description on the use of ATES3 and its validation for...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18092629
The finite-element method for multigroup neutron transport: anisotropic scattering in 1-D slab geometryRiyait, N.S. (Imperial Coll. of Science and Technology, London (UK). Nuclear Power Group); Ackroyd, R.T. (Queen Mary Coll., London (UK). Dept. of Nuclear Engineering)</br>Proof-tests on 1-D multigroup neutron transport problems are reported for strong anisotropic scattering. These tests have been undertaken as part of the validation of the 3-D multigroup finite-element transport code FELTRAN for anisotropic...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18032480
A finite element model for multigroup neutron transport with anisotropic scattering and arbitrary geometrie domainsOliveira, C.R.E. de (Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil))</br>A variational finite element-spherical harmonics method is presented for the solution of the even-parity multigroup equations with anisotropic scattering and sources. It is shown that by using a simple and natural formulation the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14802780
Construction of equiprobable bins for Monte Carlo calculationsHendricks, J.S. (LASL, Los Alamos, NM 87545)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:7246179
New definition of the cell diffusion coefficientKoehler, P. (Swiss Federal Inst. for Reactor Research, Wuerenlingen)</br>As was shown in a recent work by Gelbard, the usually applied Benoist definition of the cell diffusion coefficient gives two different values if two different definitions of the cell are made. A new definition is proposed that preserves...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9390676
C/sub N/ method of solving the transport equation: application to cylindrical geometryKavenoky, A. (Centre d'Etudes Nucleaires de Saclay, Gif-sur-Yvette, France)</br>The C/sub N/ method of solving the transport equation is applied to one-velocity classical problems in cylindrical geometry. The cylindrical angular Green's function is calculated first, the inner and outer albedo problems are solved,...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:37106928
Neutron Flux Perturbations due to Infinite Plane Absorbers IV: The Exponential Flux RevisitedWilliams, M.M.R.</br>Flux depression factors and measures of asymmetry are presented for an absorbing and scattering slab in an infinite medium in which there is an overall exponential flux. One speed transport theory is employed. The effect of the slab...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:28022585
Advances in radiation transport theory by invariant embeddingShimizu, A. (Energy Research Center, Tsuruga, Fukui (Japan))</br>This paper describes recent advances in the transport theory by the method of invariant embedding applicable to the transport problems of gamma rays and neutrons with realistic cross-sections. It includes the following three topics:...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:18078408
The spherical harmonics method for the multigroup transport equation in x-y geometryKobayashi, K.; Oigawa, H.; Yamagata, H. (Kyoto Univ. (Japan). Faculty of Engineering)</br>A spherical harmonics equation in the form of a second-order differential equation is derived for the 2-D x-y geometry, including higher-order scattering within a group. Using this equation, a multigroup transport code for the spherical...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:31019474
Validation of the VITAMIN-B6 and BUGLE-96 cross-section libraries for moderate-energy neutron and photon transport calculationsSlater, C.O.; Hunter, H.T.</br>Oak Ridge National Lab., TN (United States)</br>Newly produced multigroup cross-section libraries require detailed testing to ensure that they are suitable for the applications intended. This requires that the libraries be tested against approved experimental benchmarks and/or...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:51027608
Computation of fundamental time-eigenvalue of the neutron transport equationShen, Huayun; Zhong, Bin; Liu, Huipo (Institute of Applied Physics and Computational Mathematics, Department 6, No. 2. Fenghaodong Road, Haidian District, Beijing, 100094 (China)), E-mail: shen_huayun@iapcm.ac.cn</br>Highlights: •A modified α − k power iteration method is presented for computing the time-eigenvalue. •It is not required to provide the initial values of α for the modified method. •Computational experiences validate the validity...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:10457491
The migration area and intergeneration correlationsHughes, R.P.</br>Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs</br>It is shown that the migration area is not simply related to the mean square distance travelled by a neutron from birth to fission, but that intergeneration terms must be included. (author)
http://inis.iaea.org/Search/search.aspx?orig_q=RN:39039314
The reflected critical slab problem for one-speed neutrons with strongly anisotropic scatteringOeztuerk, H. (Osmaniye Korkut Ata Univ., Osmaniye (Turkey). Technical and Vocational School of Higher Education)</br>The Chebyshev polynomial approximation is used to solve the reflected critical slab problem for one-speed neutrons in a slab with strongly anisotropic scattering. The scattering kernel which is a combination of backward-forward-isotropic...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:48052980
The NJOY Nuclear Data Processing System, Version 2016Macfarlane, Robert (Los Alamos National Lab. (LANL), Los Alamos, NM (United States)); Muir, Douglas W. (Los Alamos National Lab. (LANL), Los Alamos, NM (United States)); Boicourt, R. M. (Los Alamos National Lab. (LANL), Los Alamos,...</br>Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA) (United States)</br>The NJOY Nuclear Data Processing System, version 2016, is a comprehensive computer code package for producing pointwise and multigroup cross sections and related quantities from evaluated nuclear data in the ENDF-4 through ENDF-6...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:40108937
Calculation procedure of effective and spectral and group neutron constants with taking into account motion of medium nucleiBnyatov, A.V.; Grebennikov, A.N.; Farafontov, G.G. (FGUP RFYaTs-VNIIEhF, ITMF, Sarov (Russian Federation))</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:16056466
The albedo problem in the case of multiple synthetic scattering taking place in a plane-symmetric slabShafiq, A.; Meyer, H.E. de; Grosjean, C.C. (Ghent Rijksuniversiteit (Belgium). Seminarie voor Wiskundige Natuurkunde)</br>The albedo problem for a slab in the presence of synthetic scattering as a substitute for anisotropic scattering is treated within the framework of time-independent one-velocity transport theory. The transport equation is transformed...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:51049993
Application of inverse gamma transport to material thickness identification with SGRD codeHumbert, P. (CEA, DAM Ile de France, Bruyeres-le-Chatel, 91297 Arpajon (France))</br>SGRD (Spectroscopy, Gamma rays, Rapid Deterministic) code is used to infer the dimensions of a one-dimensional model of a shielded gamma ray source. The method is based on the simulation of the un-collided leakage current of discrete...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9366209
Geometric interpretation of optimal iteration strategiesJones, R.B.</br>Sandia Labs., Albuquerque, N.Mex. (USA)</br>The relationship between inner and outer iteration errors is extremely complex, and even formal description of total error behavior is difficult. Inner and outer iteration error propagation is analyzed in a variational formalism for...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:9414822
Ssub(n) code for one-dimensional cylindrical geometryLemanska, M.; Shatz, M.</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:44032662
Application of MCNP in multigroup neutron transport calculationHuang Weibing; Chen Lunshou (Sanmen Nuclear Power Company, Taizhou (China)); Wu Hongchun (Xi'an Jiaotong Univ., Xi'an (China))</br>The details about how to use MCNP to solve multigroup transport problem is introduced. Some critical and fixed source cases are calculated by using MCNP, the results are in good agreement with the reference values. The successful...
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:15018404
Monte Carlo treatment of neutron diffusion in latticesGelbard, E.M. (Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:34045842
Birman-Schwinger principle and Nelkin conjecture theory of neutron transportStepin, S.A. (Moskovskij Gosudarstvennyj Univ. im. M.V. Lomonosova, Moscow (Russian Federation))</br>The work is dedicated to studying the spectral properties of the operator model, appearing in the neutron transport theory. The operator L under the consideration, corresponds to the Boltzmann linearized equation, describing the neutron...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11564027
Remarks on criticality problems for slabs and spheres in energy-dependent neutron transportVictory, H.D. Jr.; Mong, K.K. (Texas Tech Univ., Lubbock (USA))</br>This work outlines the generalization to the energy dependent case of some of the methods used to analyze multigroup and monoenergetic critical slab problems. New results for transport in energy-dependent spherical media are given....
http://inis.iaea.org/Search/search.aspx?orig_q=RN:15004486
THEMIS-4: a coherent punctual and multigroup cross section library for Monte Carlo and SN codes from ENDF/B4Dejonghe, G.; Gonnord, J.; Monnier, A.; Nimal, J.C.</br>CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)</br>The THEMIS cross section processing system has been developped to produce punctual data for MONTE CARLO and coherent multigroup data for SN codes from ENDF/B. The THEMIS-4 data base has been generated from ENDF/B4 using the system...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:45059265
Comparison research and analysis of multi-group adjoint calculation and forward calculation based on MCNPWang Chao (Beijing Graduate School of China Academy of Engineering Physics (China)); Deng Li (Institute of Applied Physics and Computational Mathematics, Beijing (China))</br>In order to investigate the agreement and difference between adjoint and forward calculations with Monte Carlo method, three models have been simulated, and the calculated results are compared and analyzed. First, the comparison shows...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12608022
Radioactive materials packages and the British railway accident environmentTaig, A.R. (UKAEA, Warrington. Safety and Reliability Directorate)</br>No abstract available.
http://inis.iaea.org/Search/search.aspx?orig_q=RN:25070453
Policies to reconcile economic issuesGoodwin, P.B. (Oxford Univ. (United Kingdom). Transport Studies Unit)</br>Accepting the proposition that it is not possible to build enough new road capacity to match the projected increases in traffic, it is therefore necessary to give priority to essential passenger and freight movement (by traffic management...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:28032432
Anisotropic scattering in the variational nodal simplified spherical harmonics formulationLewis, E.E. (Northwestern Univ., Evanston, IL (United States))</br>Under the assumption of isotropic scattering, the simplified spherical harmonics method (SP<sub>N</sub>) was recently formulated in variational nodal form and implemented successfully as an option of the VARIANT code. In this paper,...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:20043557
A nodal solution of the multigroup neutron transport equation using spherical harmonicsInanc, F.; Rohach, A.F. (Iowa State Univ. of Science and Technology, Ames (USA). Dept. of Nuclear Engineering)</br>A nodal method has been developed for solving the neutron transport equation using spherical harmonics in 2-D Cartesian coordinates for rectangular nodes. The first-order differential equations resulting from the expansion of the...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:14717731
Theory of nuclear reactors. Vol. 1. 2. rev. ed.Emendoerfer, D.; Hoecker, K.H. (Stuttgart Univ. (Germany, F.R.). Inst. fuer Kernenergetik und Energiesysteme)</br>An introduction is given to the elements of reactor physics and reactor calculation which refers to practice from the present point of view. It is demonstrated to the reader how the reactor characteristics relevant to construction...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:11530174
Calculation of cell volumes and surface areas in MCNPHendricks, J.S.</br>Los Alamos Scientific Lab., NM (USA)</br>MCNP is a general Monte Carlo neutron-photon particle transport code which treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree...
http://inis.iaea.org/Search/search.aspx?orig_q=RN:12598342
Overview of TRIPOLI 2Baur, A.; Bourdet, L.; Dejonghe, G.; Gonnord, J.; Monnier, A.; Nimal, J.C.; Vergnaud, T. (CEA, Saclay, France)</br>The tridimensional Monte Carlo code TRIPOLI 2, which solves transport problems for neutrons or gamma rays, is presented. This code is used either for shielding calculations with deep penetration or for core calculations with fixed...