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Results 1 to 25 of 110

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STRUCTURAL ANALYSIS OF SHIPPING CASKS. XII. ENERGY ABSORPTION CHARACTERISTICS OF STAINLESS STEEL BOLTS UNDER IMPACT LOADINGCANNON DE.1972; ORNL-TM-1312 (VOL. 12); U.S.A.; DA. 1972; PP. 1-114; BIBL. 12 REF.; MICROFICHEReport

ANALYSES OF A SHIPPING CASK (MODEL FSV-2) FOR TRANSPORTATION OF MIXED FISSION PRODUCTSREESER HG.1972; GULF-GA-A-10890; U.S.A.; DA. 1972; PP. (115 P.); BIBL. 30 REF.; MICROFICHEReport

STEEL BANDED WOODEN SHIPPING CONTAINERS FOR SLIGHTLY ENRICHED URANIUM BILLETS, INGOTS AND FUEL CORESDUNAWAY DL.1972; NLCO-1089; U.S.A.; DA. 1972; PP. (18 P.); BIBL. 8 REF.; MICROFICHEReport

AN IMPROVED SHIPPING CONTAINER FOR FISSILE MATERIALGASKILL JR; TAYLOR RD.1972; UCRL-14903; U.S.A.; DA. 1972; PP. (37 P.); MICROFICHEReport

SHIPMENT AND REPROCESSING OF IRRADIATED POWER REACTOR FUELSSMITH CW.1972; IN: EDUC. RES. NUCL. FUEL CYCLE; UNIV. OKLAHOMA; 1970; S.L.; UNIV. OKLAHOMA; DA. 1972; PP. 137-151Conference Proceedings

ANALYSIS OF THE ORNL LOOP TRANSPORT CARRIERWATKIN DC.1972; ORNL-TM-3744; U.S.A.; DA. 1972; PP. (80 P.); BIBL. 14 REF.; MICROFICHEReport

TRANSPORTBEHAELTER FUER RADIOAKTIVE GROSSQUELLEN = CHATEAU DE TRANSPORT POUR LES GRANDES SOURCES RADIOACTIVESSCHULZ FORBERG B.1972; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1972; VOL. 17; NO 11; PP. 570-573; ABS. ANGL. FR.; BIBL. 5 REF.Serial Issue

LEAD SHIELDING CALCULATIONS FOR TRANSPORT CONTAINERS FOR COMMONLY USED RADIOISOTOPESSHAIKH MU.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 23; NO 2; PP. 228-234; BIBL. 8 REF.Serial Issue

QUELQUES PROBLEMES INDUSTRIELS OU LA CONVECTION NATURELLE JOUE UN ROLE IMPORTANTGROSSIN R.1972; REV. GEN. THERM.; FR.; DA. 1972; VOL. 11; NO 126; PP. 543-554Serial Issue

The single SNR fuel assembly container (ESBB) to transport unirradiated SNR 300 fuel assembliesHILBERT, F; HOTTENROTT, G.International conference on the packaging and transportation of radioactive materials. 1998, pp 728-734, 4VolConference Paper

Design of spent-fuel concrete pit dry storage and handling systemTAMAKI, H; NATSUME, T; MARUOKA, K et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1659-1664, 4VolConference Paper

A flexible cask design for transporting high-level and other wasteZIMMER, A.International conference on the packaging and transportation of radioactive materials. 1998, pp 1426-1429, 4VolConference Paper

The R66 cask, a lead-shielded type B cask development of a new containment conceptBERA, R. C; BOCHARD, C. M; COSTON, C et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 411-413, 4VolConference Paper

The problem of manufacturing spent nuclear fuel storage and transportation casks in RussiaZUBKOV, A. A; FROMZEL', V. N; KAPILEVICH, A. N et al.Thermal engineering. 2002, Vol 49, Num 5, pp 369-371, issn 0040-6015Article

Dose rates calculation exterior to the container used for transportation of the WWR-S NIPNE-HH reactor spent fuelENE, D.International symposium on nuclear energy. 1999, pp 289-292, 2VolConference Paper

Dual/multi purpose canisters and the reprocessing optionROLAND, V; HANSON, A.International conference on the packaging and transportation of radioactive materials. 1998, pp 414-419, 4VolConference Paper

Fabrication & testing of the TN-FSV transport caskGUERRA, G. V.International conference on the packaging and transportation of radioactive materials. 1998, pp 1037-1044, 4VolConference Paper

Strength analysis of the constor steel-concrete cask model under dynamic testsDREIER, G; DIERSCH, R; NIKITIN, V et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1247-1254, 4VolConference Paper

Spent fuel transportation with the TN-MTR packagingANNE, Catherine; GALTIER, Jérome.International topical meeting on research reactor fuel management. 2000, pp 80-82Conference Paper

Extension of ship accident analysis to multiple-package shipmentsMILLS, G. S; NEUHAUSER, K. S.International conference on the packaging and transportation of radioactive materials. 1998, pp 753-759, 4VolConference Paper

Demonstration test of a shipping cask for high burnup spent fuels : VIDEO of drop test, thermal test and water immersion testSATOH, K; ITOH, C; KOMATSU, S et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1653-1658, 4VolConference Paper

Safety assessment of leaktightness criteria for radioactive materials transport packagesKOWALEWSKY, H; DROSTE, B; NEUMEYER, T et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 543-550, 4VolConference Paper

The TN-MTR packagingMICHELS, L; BRACEY, W.International conference on the packaging and transportation of radioactive materials. 1998, pp 397-402, 4VolConference Paper

Transport and storage casks for irradiated fuel assemblies from research reactorsWEISS, M.International conference on the packaging and transportation of radioactive materials. 1998, pp 1395-1399, 4VolConference Paper

Characteristics of upper-bound fuel rods for criticality studies of fuel assembly transport casksBAGARRY, M; COUSINOU, P.International conference on the packaging and transportation of radioactive materials. 1998, pp 224-230, 4VolConference Paper

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