Effect of systematic error in the fuel mass on k_eff in pebble bed reactors : Selected and expanded papers from International Conference Nuclear Energy for New Europe 2010, Portoroz, Slovenia, September 6-9, 2010RADULOVIC, Vladimir; LENGAR, Igor; TRKOV, Andrej et al.Nuclear engineering and design. 2012, Vol 246, pp 75-81, issn 0029-5493, 7 p.Article

Assessment of on-line bumup monitoring of pebble bed reactor fuel by passive neutron countingBINGJING SU; ZHONGXIONG ZHAO; JIANWEI CHEN et al.Progress in nuclear energy (New series). 2006, Vol 48, Num 7, pp 686-702, issn 0149-1970, 17 p.Article

Mechanism analysis of quasi-static dense pebble flow in pebble bed reactor using phenomenological approachYANG, X. T; HU, W. P; JIANG, S. Y et al.Nuclear engineering and design. 2012, Vol 250, pp 247-259, issn 0029-5493, 13 p.Article

Investigation of bounds on particle packing in pebble-bed high temperature reactorsDUGOUAG, Abderrafi M; KLOOSTERMAN, Jan Leen; VAN ROOIJEN, Wilfred F. G et al.Nuclear engineering and design. 2006, Vol 236, Num 5-6, pp 669-676, issn 0029-5493, 8 p.Conference Paper

ENTWICKLUNG UND ENTWICKLUNGSTENDENZEN VON KERNKRAFTWERKEN MIT HOCHTEMPERATURREAKTOREN. = DEVELOPMENT AND TRENDS OF HTR NUCLEAR POWER PLANTS = NIVEAU ET TENDANCES DE DEVELOPPEMENT DES CENTRALES NUCLEAIRES A REACTEURS HAUTE TEMPERATUREHIRSCHFELDER G.1977; V.G.B. KRAFTWERKSTECH.; DTSCH.; DA. 1977; VOL. 57; NO 1; PP. 8-16; ABS. ANGL. DAIS FR. NEERL. ITAL. SUEDOISArticle

NUMERISCHE UNTERSUCHUNGEN ZUM BRENNSTOFFKREISLAUF EINES 10 GW_TH OTTO-KUGELHAUFENREAKTORS IM HINBLICK AUF EINE HOHE KONVERSIONSRATE UNTER BESONDERER BERUECKSICHTIGUNG DER ABSONDERUNG VON U-236 DURCH ISOTOPENTRENNUNG = NUMERICAL INVESTIGATIONS OF THE FUEL CYCLE FOR A 10 GW_TH-OTTO-PEBBLE-BED REACTOR WITH REGARD TO HIGH CONVERSION RATIO UNDER SPECIAL CONSIDERATION OF U-236 ELIMINATION BY ISOTOPE SEPARATION = ETUDES NUMERIQUES DU CYCLE DU COMBUSTIBLE D'UN REACTEUR OTTO A LIT DE BOULETS DE 10 GW_TH EN VUE D'OBTENIR UN TAUX DE CONVERSION ELEVE EN CONSIDERANT SPECIALEMENT L'ELIMINATION DE U-236 PAR SEPARATION ISOTOPIQUEWERNER H.1977; BER. KERNFORSCH.-ANLAGE FUELICH; DTSCH.; DA. 1977; NO 1365; PP. 1-94; ABS. ANGL.; BIBL. 1 P. 1/2Serial Issue

CONTRIBUTIONS TO THE SAFETY-ANALYSIS OF PEBBLE-BED HTRS. = CONTRIBUTIONS A L'ANALYSE DE SECURITE DES REACTEURS A HAUTE TEMPERATURE A LIT DE BOULETSSCHARF J; VIGASSY J.1976; ANN. NUCL. ENERGY; G.B.; DA. 1976; VOL. 3; NO 4; PP. 211-214; BIBL. 8 REF.Article

DEVELOPMENT AND TESTING OF NUCLEAR GRAPHITES FOR THE GERMAN PEBBLE-BED HTRJANSSEN K; O'CONNOR MF; HAAG G et al.1981; BIENNIAL CONFERENCE ON CARBON. 15/1981/PHILADELPHIA PA; USA; PHILADELPHIA: THE UNIVERSITY OF PENNSYLVANIA; DA. 1981; PP. 544-545; BIBL. 3 REF.Conference Paper

EINBEZIEHUNG DER SPALTPRODUKTFREISETZUNG IN DIE NUMERISCHE SIMULATION DES AVR-ABBRAND-UMWAELZGESCHEHENS UND VERGLEICH MIT DEN VAMPYR-RESULTATEN = INCLUSION OF FISSION PRODUCT RELEASE IN THE NUMERICAL MODEL OF AVR FUEL CYCLE AND COMPARISON WITH VAMPYR EXPERIMENT DATA = INTRODUCTION DU DEGAGEMENT DE PRODUITS DE FISSION DANS LA SIMULATION NUMERIQUE DU CYCLE DU COMBUSTIBLE DU REACTEUR AVR ET COMPARAISON AVEC LES RESULTATS DE L'ESSAI VAMPYRWEBER J.1979; BER. KERNFORSCH.-ANLAGE JUELICH; DEU; DA. 1979; NO 1570; 119 P.; ABS. ENG; BIBL. 48 REF.Article

FLOW OF INDIVIDUAL PEBBLES IN CYLINDRICAL VESSELS.GATT FC.1977; NUCL. ENGNG DESIGN; NETHERL.; DA. 1977; VOL. 42; NO 2; PP. 265-275; BIBL. 6 REF.Article

WERKSTOFFENTWICKLUNG FUER GASGEKUEHLTE HOCHTEMPERATURREAKTOREN ZUR ERZENGUNG NUKLEARER PROZESSWAERME. = DEVELOPMENT OF MATERIALS FOR GAS-COOLED HIGH TEMPERATURE REACTORS FOR GENERATING NUCLEAR PROCESS HEAT = DEVELOPPEMENT DES MATERIAUX POUR REACTEURS A TEMPERATURE ELEVEE REFROIDIS PAR GAZ POUR LA PRODUCTION DE CHALEUR NUCLEAIRENICKEL H.1977; CHEM.-INGR-TECH.; DTSCH.; DA. 1977; VOL. 49; NO 8; PP. 639-650; BIBL. 25 REF.Article

NUMERISCHE BERECHNUNG DES TRITIUM-VERHALTENS VON KUGELHAUFENREAKTOREN AM BEISPIEL DES AVR-REAKTORS = NUMERICAL CALCULATION OF THE TRITIUM-BEHAVIOUR OF PEBBLE-BED REACTORS DEMONSTRATED ON THE AVR REACTOR = CALCUL NUMERIQUE DU COMPORTEMENT VIS-A-VIS DU TRITIUM DES REACTEURS A LIT DE BOULETS SUR L'EXEMPLE DU REACTEUR AVRCORDEWINER HJ.1979; BER. KERNFORSCH.-ANLAGE JUELICH; DEU; DA. 1979; NO 1607; (115 P.); ABS. ENG; BIBL. 35 REF.Serial Issue

ZUM HEAD-END DER AUFARBEITUNG VON HTR-BRENNELEMENTEN = THE HEAD END OF A REPROCESSING PLANT FOR HTR FUEL ELEMENTS = LE PREMIER ETAGE DE RETRAITEMENT DES ELEMENTS COMBUSTIBLES DE REACTEURS A HAUTE TEMPERATURETISCHER H; HARTMANN K.1979; ATOMWIRTSCH. ATOMTECH.; DEU; DA. 1979; VOL. 24; NO 6; PP. 331-333; ABS. ENG/FRE; BIBL. 9 REF.Article

Fuel burnup performance of an OTTO refueling pebble bed reactor with burnable poison loadingNAM TRAN, Hoai.Progress in nuclear energy (New series). 2012, Vol 60, pp 47-52, issn 0149-1970, 6 p.Article

Turbulence-induced heat transfer in PBMR core using LES and RANSLEE, Jung-Jae; YOON, Su-Jong; PARK, Goon-Cherl et al.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 7, pp 985-996, issn 0022-3131, 12 p.Article

The effective thermal conductivity of a bed of 1.2-mm-diam lithium zirconate spheres in heliumEARNSHAW, J. W; LONDRY, F. A; GIERSZEWSKI, P. J et al.Fusion technology. 1998, Vol 33, Num 1, pp 31-37, issn 0748-1896Article

NEW STRATEGY ON THE EVALUATION OF DANCOFF FACTOR IN A PEBBLE BED REACTOR USING MONTE CARLO METHODSONG HYUN KIM; KIM, Hong-Chul; JONG KYUNG KIM et al.Nuclear technology. 2012, Vol 177, Num 2, pp 147-156, issn 0029-5450, 10 p.Article

A CFD method to evaluate the integrated influence of leakage and bypass flows on the PBMR Reactor UnitJANSE VAN RENSBURG, J. J; KLEINGELD, M.Nuclear engineering and design. 2010, Vol 240, Num 11, pp 3841-3850, issn 0029-5493, 10 p.Article

The AVR nuclear power plant ― A milestone in high-temperature reactor developmentSCHULTEN, R.Nuclear science and engineering. 1985, Vol 90, Num 4, pp 388-390, issn 0029-5639Article

Das technische Konzept des HTR-500 = Conception technique du HTR-500 = The technical concept of the HTR-500BAUST, E; WITTCHOW, G; SCHONING, J et al.Atomkernenergie, Kerntechnik. 1985, Vol 47, Num 3, pp 145-148, issn 0171-5747Article

The AVR* nuclear power facility. Progress reportZIERMANN, E.Nuclear engineering and design. 1984, Vol 78, Num 2, pp 99-108, issn 0029-5493Article

Aufbau eines dreidimensionalen Simulationsverfahrens zur corephysikalischen Beschreibung von Kugelhaufenreaktoren mit Mehrfachdurchlauf am Beispiel des AVR = Développement d'un procédé de simulation tridimensionnelle pour la description du comportement physique du cœur de réacteurs à lit de boulets à passage multiple sur l'exemple du réacteur AVR = Development of a three-dimensional simulation method for core-physical description of pebble bed reactors with multiple pass on the example of the AVRGROTKAMP, T.Berichte der Kernforschungsanlage Jülich. 1984, Num 1888, issn 0366-0885, 81 p.Thesis

Neutronic characteristics of an OTTO refueling PBMRHOAI NAM TRAN; VAN KHANH HOANG.Nuclear engineering and design. 2012, Vol 253, pp 269-276, issn 0029-5493, 8 p.Article

A semi-theoretical approach to a correlation for the thermal conductivity of a Beryllium pebble bedDI MAIO, P. A; VELLA, G.Heat transfer engineering. 2003, Vol 24, Num 5, pp 38-46, issn 0145-7632, 9 p.Article

Mechanisches Verhalten des Hochtemperaturreaktorkerns unter seismischen Belastungen = Comportement mécanique du cœur d'un réacteur à haute température sous charges sismiques = The mechanical behaviour of a high-temperature reactor core under seismic loadingsBODMANN, E; KLEINE-TEBBE, A.Atomkernenergie, Kerntechnik. 1985, Vol 47, Num 3, pp 184-187, issn 0171-5747Article