Pascal-Francis CNRS

Pascal and Francis Bibliographic Databases

Help

Search results

Your search

kw.\*:("Transport neutron")

Filter

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Document Type [dt]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Publication Year[py]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Discipline (document) [di]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Language

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Author Country

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Origin

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Results 1 to 25 of 499

  • Page / 20
Export

Selection :

  • and

L1 convergence of the discrete ordinates for the neutron transport equation in an infinite cyclindrical domainASADZADEH, M.Nuclear science and engineering. 1992, Vol 112, Num 4, pp 383-391, issn 0029-5639Article

A simple derivation of the neutron transport equationPAZSIT, I.Nuclear science and engineering. 1992, Vol 112, Num 4, pp 369-374, issn 0029-5639Article

Neutron and photon transport in Fe with the employment of TENDL 2009, CENDL 3.1, JENDL 4 and JENDL 4 evolution from JENDL 3.3 in case of FeKOST'AL, Michal; CVACHOVEC, František; CVACHOVEC, Jiří et al.Nuclear engineering and design. 2012, Vol 249, pp 275-286, issn 0029-5493, 12 p.Article

BR2 reactor core steady state and transient modelingMAKARENKO, A; PETROVA, T.International topical meeting on research reactor fuel management. 2000, pp 111-115Conference Paper

Positive solutions for reactor multigroup neutron transport systems: critically problemGEN-SHUN CHEN; LEUNG, A. W.SIAM journal on applied mathematics (Print). 1989, Vol 49, Num 3, pp 871-887, issn 0036-1399Article

Auto MOC-A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCADQICHANG CHEN; HONGCHUN WU; LIANGZHI CAO et al.Nuclear engineering and design. 2008, Vol 238, Num 10, pp 2828-2833, issn 0029-5493, 6 p.Article

Non-local electron transport in laser-produced plasmasSUNAHARA, A; MIMA, K; JOHZAKI, T et al.Journal de physique. IV. 2006, Vol 133, pp 193-195, issn 1155-4339, 3 p.Conference Paper

Coarse-mesh angular dependent rebalance acceleration of the discrete ordinates transport calculationsYOUNG RYONG PARK; NAM ZIN CHO.Nuclear science and engineering. 2004, Vol 148, Num 3, pp 355-373, issn 0029-5639, 19 p.Article

Parallelization of neutron transport solversROY, R; STANKOVSKI, Z.Lecture notes in computer science. 1997, pp 494-501, issn 0302-9743, isbn 3-540-63697-8Conference Paper

Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel latticeYOUQI ZHENG; HONGCHUN WU; LIANGZHI CAO et al.Nuclear engineering and design. 2009, Vol 239, Num 10, pp 1804-1810, issn 0029-5493, 7 p.Article

The FN solution of the neutron transport equation with synthetic scatteringYILDIZ, C.Il Nuovo cimento. B. 1989, Vol 103, Num 2, pp 195-202, issn 0369-3554, 8 p.Article

TIME DEPENDENT NEUTRON TRANSPORT THEORY FOR HOMOGENEOUS FAST MULTIPLYING SYSTEMSGRUNDMANN U.1973; KERNENERGIE; DTSCH.; DA. 1973; VOL. 16; NO 12; PP. 52-56; BIBL. 10 REF.Serial Issue

DIFFUSION LENGTH OF NEUTRONS IN GRAPHITE-BISMUTH MIXTURESBHUSHAN V.1972; J. NUCL. ENERGY; G.B.; DA. 1972; VOL. 26; NO 5; PP. 271-273; BIBL. 7 REF.Serial Issue

A stationary criticality problem in general Lp-space for energy dependent neutron transport in cylindrical geometryBORGIOLI, G; FROSALI, G.Zeitschrift für angewandte Mathematik und Physik. 1984, Vol 35, Num 2, pp 166-180, issn 0044-2275Article

Simultaneous Monte Carlo zero-variance estimates of several correlated meansBOOTH, T. E.Nuclear science and engineering. 1998, Vol 129, Num 2, pp 199-202, issn 0029-5639Article

Foundations of finite element applications to neutron transportACKROYD, R. T.Progress in nuclear energy (New series). 1995, Vol 29, Num 1, pp 43-56, issn 0149-1970Article

Tibere : une méthode de calcul de l'effet de l'hétérogénéïté d'un réseau sur les fuites de neutrons = Tibere : a calculational method of the effect of lattice heterogeneity on the neutron leakageBenoist, Pierre; Petrovic, Ivan.1992, 69 p.Report

Monte Carlo estimates of transport solutions to the isotropic slab problemBOOTH, T. E.Nuclear science and engineering. 1998, Vol 130, Num 3, pp 374-385, issn 0029-5639Article

Etudes des incertitudes sur la fluence dans les cuves des REP. Ajustement des données de base = Uncertainty study of the PWR pressure vessel fluence. Adjustment of the nuclear data baseKodeli, Ivan; Nimal, Jean-Claude.1993, 138 p.Thesis

COMPUTATIONAL EXPERIMENTATION ON THE FINITE ELEMENT METHOD IN BARE SLAB CRITICALITY CALCULATIONSPITKARANTA J; SILVENNOINEN P.1973; NUCL. SCI. ENGNG; U.S.A.; DA. 1973; VOL. 50; NO 3; PP. 297-300; BIBL. 9 REF.Serial Issue

SOLUTION DES PROBLEMES DE DIFFUSION DES NEUTRONS DANS LES REACTEURS BIDIMENSIONNELS HETEROGENES PAR UNE METHODE DE VARIATIONS DIRECTESISAEV NV; SLESAREV IS.sdATOM. ENERG.; S.S.S.R.; DA. ,(19; VOL. 34; NO 3; PP. 194; BIBL. 3 REF.; RES. DE L'ART. NO 652-6911 DEPOSE A LA REDACTION DE CE PERSerial Issue

DISCRETE ORDINATE NEUTRON TRANSPORT EQUATION EQUIVALENT TO PL APPROXIMATIONJUNGCHUNG JUNG; CHIJIWA H; KOBAYASHI K et al.1972; NUCL. SCI. ENGNG; U.S.A.; DA. 1972; VOL. 49; NO 1; PP. 1-9Serial Issue

Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problemBÜLBÜL, A; ANLI, F.Kerntechnik (1987). 2008, Vol 73, Num 4, pp 163-166, issn 0932-3902, 4 p.Article

Diffusion limit for the linear Boltzmann equation of the neutron transport theoryBANASIAK J; MIKA, J. R.Mathematical methods in the applied sciences. 1994, Vol 17, Num 13, pp 1071-1087, issn 0170-4214Article

Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equationYOUQI ZHENG; HONGCHUN WU; LIANGZHI CAO et al.Nuclear engineering and design. 2013, Vol 254, pp 142-147, issn 0029-5493, 6 p.Article

  • Page / 20