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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

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

EXACT SOLUTION OF TRANSPORT EQUATION IN FINITE MULTIPLYING MEDIADAS GUPTA SR; BISHNU SK.1981; ASTROPHYS. SPACE SCI.; ISSN 0004-640X; NLD; DA. 1981; VOL. 74; NO 1; PP. 131-147; BIBL. 8 REF.Article

SOLUTION OF MULTI-DIMENSIONAL NEUTRON TRANSPORT EQUATION BY FINITE ELEMENT METHODUKAI S.1972; J. NUCL. SCI. TECHNOL.; JAP.; DA. 1972; VOL. 9; NO 6; PP. 366-373; BIBL. 21 REF.Serial Issue

SUBTHERMAL PULSED NEUTRON MEASUREMENTS IN POLYCRYSTALLINE MEDIARZESZOT T; WARDA E.1972; J. NUCL. ENERGY; G.B.; DA. 1972; VOL. 26; NO 8; PP. 419-429; BIBL. 9 REF.Serial Issue

INFLUENCE DU CHAMP MAGNETIQUE SUR LA DIFFUSION DES NEUTRONS ET POSSIBILITE DE REGULATION MAGNETIQUE DES REACTEURSORLOV VV; KAZACHENKOV YU N.1972; ATOM. ENERG.; S.S.S.R.; DA. 1972; VOL. 33; NO 2; PP. 710-711; BIBL. 3 REF.Serial Issue

ON NONLINEAR NEUTRON TRANSPORT EQUATIONSPAO CV.1973; J. MATH. ANAL. APPL.; U.S.A.; DA. 1973; VOL. 42; NO 3; PP. 578-593; BIBL. 15 REF.Serial Issue

SOLUTION OF A NONLINEAR BOLTZMANN EQUATION FOR NEUTRON TRANSPORT IN L1 SPACEPAO CV.1973; ARCH. RATION. MECH. ANAL.; GERM.; DA. 1973; VOL. 50; NO 4; PP. 290-302; BIBL. 16 REF.Serial Issue

SUR LE CALCUL DU RALENTISSEMENT DES NEUTRONS SUBTHERMIQUES PAR UN SYSTEME DE MIROIRS NEUTRONIQUES PLANS TOURNANTKASHUKEEV NT; MIRCHEVA DS; YANEVA NB et al.1973; C.R. ACAD. BULG. SCI.; BULG.; DA. 1973; VOL. 26; NO 1; PP. 51-54; BIBL. 4 REF.Serial Issue

EXISTENCE AND UNIQUENESS OF THE SOLUTION TO THE CRITICAL PROBLEM IN THE MULTIGROUP NEUTRON-TRANSPORT THEORYBORYSIEWICZ M; MIKA J.1972; TRANSP. THEORY STATIST. PHYS.; U.S.A.; DA. 1972; VOL. 2; NO 3; PP. 243-270; BIBL. 15 REF.Serial Issue

ON THE THEORY OF PULSED-NEUTRON EXPERIMENTS IN POLYCRYSTALLINE MODERATORSBEAUWENS R; MIKA J.1972; TRANSP. THEORY STATIST. PHYS.; U.S.A.; DA. 1972; VOL. 2; NO 2; PP. 91-108; BIBL. 22 REF.Serial Issue

A MODIFIED VARIATIONAL METHOD FOR THE PULSED-NEUTRON PROBLEMFEROZ AHMED; RANGASWAMY L; KOTHARI LS et al.1972; TRANSP. THEORY STATIST. PHYS.; U.S.A.; DA. 1972; VOL. 2; NO 3; PP. 197-209; BIBL. 7 REF.Serial Issue

CALCULATION AND MEASUREMENT OF NEUTRON-PRODUCED SINGLE-EVENT SPECTRAOLDENBURG U; BOOZ J.1972; RAD. RES.; U.S.A.; DA. 1972; VOL. 51; NO 3; PP. 551-568; BIBL. 20 REF.Serial Issue

PHOTON TRANSPORT AND THE CRITICAL PROBLEM.SELDEN AC.1975; PHYSICA B+C; PAYS-BAS; DA. 1975; VOL. 79; NO 4; PP. 409-418; BIBL. 26 REF.Article

APPLICATION DE LA METHODE DE GALERKIN A LA RESOLUTION DE L'EQUATION INTEGRALE DU TRANSPORT UNIDIMENSIONNELLE: PROBABILITES DE COLLISIONS GENERALISEES TENANT COMPTE DU GRADIENT DU FLUX ET DU CHOC LINEAIREMENT ANISOTROPE.SANCHEZ R.1974; CEA-N-1793; FR.; DA. 1974; PP. (213P.); BIBL. 3 P.; (THESE DOCT. 3E. CYCLE, SPEC. PHYS. NUCL. APPROFONDIE, OPTION PHYS. REACT.; PARIS XI ORSAY)Report

SPECTRAL ANALYSIS OF GRAPHITE PULSED NEUTRON DECAY DATAHANNA NN.1973; J. NUCL. ENERGY; G.B.; DA. 1973; VOL. 27; NO 2; PP. 118-121; BIBL. 7 REF.Serial Issue

COMPUTER SOLUTIONS OF SOME TRANSPORT PHENOMENA PROBLEMSSCHOT JW.1972; COMPUTER PHYS. COMMUNIC.; NETHERL.; DA. 1972; VOL. 4; NO 1; PP. 73-81; BIBL. 26 REF.Serial Issue

SOLUTIONS ELEMENTAIRES DE L'EQUATION DE TRANSPORT DES NEUTRONS EN CONSIDERANT LA DIFFUSION ANISOTROPESULTANOV NV.1972; ATOM. ENERG.; S.S.S.R.; DA. 1972; VOL. 32; NO 6; PP. 457-462; ABS. ANGL.; BIBL. 9 REF.Serial Issue

A SOLUTION OF THE SLOWING-DOWN OF NEUTRON EQUATION BY INTEGRAL TRANSFORMSDIAZ M.1972; REV. ROUMAINE PHYS.; ROUMAN.; DA. 1972; VOL. 17; NO 5; PP. 571-579; ABS. FR.; BIBL. 3 REF.Serial Issue

AN INVESTIGATION OF NON-EXPONENTIAL DECAY OF NEUTRON DISTRIBUTIONS IN GRAPHITEFARLANE HF.1972; NUCL. SCI. ENGNG; U.S.A.; DA. 1972; VOL. 49; NO 4; PP. 438-449; BIBL. 27 REF.Serial Issue

IMPROVED INTEGRAL TRANSPORT THEORY BY MEANS OF SPACE POLYNOMIAL APPROXIMATIONSLIGOU J.1973; NUCL. SCI. ENGNG; U.S.A.; DA. 1973; VOL. 50; NO 2; PP. 135-146; BIBL. 27 REF.Serial Issue

EFFECT OF SINGULARITIES ON APPROXIMATION IN SN METHODSARKUSZEWSKI J; KULIKOWSKA T; MIKA J et al.1972; INR-REPORT-1405-XXI-PR; POLAND; DA. 1972; PP. (25 P.); ABS. POL. RUSSE; BIBL. 1 P.Report

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