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Results 1 to 25 of 38

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HEAT CAPACITY OF PLUTONIUM NITRIDE AT LOW TEMPERATURES.HALL ROA; LEE JA; MARTIN DJ et al.1978; J. CHEM. THERMODYNAM.; GBR; DA. 1978; VOL. 10; NO 10; PP. 935-940; BIBL. 16 REF.Article

DOUBLING TIMES OF CARBIDE AND NITRIDE FUELS FOR LMFBRS = TEMPS DE DOUBLEMENT DES COMBUSTIBLES AUX CARBURES ET AUX NITRURES POUR REACTEURS SURREGENERATEURS A METAL LIQUIDE1975; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1975; VOL. 21; PP. 403-408; BIBL. DISSEM.; (AM. NUCL. SOC. ANNU. MEET.; NEW ORLEANS; 1975)Conference Paper

ETUDE THERMODYNAMIQUE A HAUTE TEMPERATURE DES CARBONITRURES DE PLUTONIUMDE FRANCO M.1974; AO-CNRS-11106; FR.; DA. 1974; PP. 1-114; BIBL. 5 P. 1/2; (THESE DOCT. SCI. PHYS.; PARIS-SUD)Thesis

CARBOTHERMIC SYNTHESIS OF PLUTONIUM MONONITRIDE FROM THE DIOXIDESUSUKI Y; ARAI Y; SASAYAMA T et al.1983; JOURNAL OF NUCLEAR MATERIALS; ISSN 0022-3115; NLD; DA. 1983; VOL. 115; NO 2-3; PP. 331-333; BIBL. 7 REF.Article

Vaporization behavior of uranium-plutonium mixed nitrideSUZUKI, Y; MAEDA, A; ARAI, Y et al.Journal of nuclear materials. 1992, Vol 188, pp 239-243, issn 0022-3115Conference Paper

The chemistry and physics of modelling nitride fuels for transmutationTHETFORD, Roger; MIGNANELLI, Mike.Journal of nuclear materials. 2003, Vol 320, Num 1-2, pp 44-53, issn 0022-3115, 10 p.Conference Paper

CARBOTHERMIC SYNTHESIS OF HIGH PURITY PLUTONIUM NITRIDE FROM PLUTONIUM OXIDEMUROMURA T.1982; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1982; VOL. 19; NO 8; PP. 638-645; BIBL. 27 REF.Article

TERNARY PHASE EQUILIBRIA IN THE SYSTEMS ACTINIDE-TRANSITION METAL-CARBON AND ACTINIDE-TRANSITION METAL-NITROGEN = EQUILIBRES DE PHASES TERNAIRES DANS LES SYSTEMES ACTINIDE-METAL TRANSITION-CARBONE ET ACTINIDE-METAL TRANSITION-AZOTEHOLLECK H.1975; IN: THERMODYN. NUCL. MATER. PROC. SYMP.; VIENNA; 1974; VIENNA; I.A.E.A.; DA. 1975; VOL. 2; PP. 213-264; BIBL. 1 P.Conference Paper

Anodic dissolution of uranium mononitride in lithium chloride-potassium chloride eutectic meltKOBAYASHI, F; OGAWA, T; AKABORI, M et al.Journal of the American Ceramic Society. 1995, Vol 78, Num 8, pp 2279-2281, issn 0002-7820Article

Electrolysis of plutonium nitride in LiCl-KCl eutectic meltsSHIRAI, O; IWAI, T; SHIOZAWA, K et al.Journal of nuclear materials. 2000, Vol 277, Num 2-3, pp 226-230, issn 0022-3115Article

Inherent stability in a fast reactor for utilizing plutoniumKUZ'MIN, A. M; OKUNEV, V. S.Atomic energy (New York, N.Y.). 1998, Vol 84, Num 6, pp 423-425, issn 1063-4258Article

Thermal conductivity of actinide mononitride solid solutionsARAI, Y; NAKAJIMA, K; SUZUKI, Y et al.Journal of alloys and compounds. 1998, Vol 271-73, pp 602-605, issn 0925-8388Conference Paper

CERAMIC UTILIZATION IN THE NUCLEAR INDUSTRY. II: CUSSENT STATUS AND FUTURE TRENDSROBERTS JTA.1979; POWDER METALLURGY INTERNATION.; DEU; DA. 1979; VOL. 11; NO 2; PP. 72-80; ABS. GER/FREArticle

LATTICE PARAMETER VARIATION OF PUC, PUN, AND PU(C,N) BETWEEN 50 AND 300 K.BENEDICT U; DUFOUR C; SCHOLTEN O et al.1978; J. MATER. NUCL.; PAYS-BAS; DA. 1978; VOL. 73; NO 2; PP. 208-212; ABS. FR. ALLEM.; BIBL. 19 REF.Article

High temperature behavior of irradiated mixed nitride fuel during heating testsSATO, Isamu; TANAKA, Kosuke; HIROSAWA, Takashi et al.Journal of alloys and compounds. 2007, Vol 444-445, pp 580-583, issn 0925-8388, 4 p.Conference Paper

Development of the thermal schemes, equipment and operating regimes of the second circuit of a promising nuclear power stationFILIN, A. I; TSIKUNOV, V. S; POPOV, S. V et al.Thermal engineering. 2001, Vol 48, Num 6, pp 458-463, issn 0040-6015Article

Status of the development and production of uranium-plutonium fuel for fast reactorsRESHETNIKOV, F. G.Atomic energy (New York, N.Y.). 2001, Vol 91, Num 6, pp 998-1002, issn 1063-4258Article

A conceptual design study on innovative FBRKASAI, S; KUBOTA, K; HAYAFUNE, H et al.Progress in nuclear energy (New series). 2000, Vol 37, Num 1-4, pp 131-136, issn 0149-1970Conference Paper

Les nouveaux combustibles pour réacteurs à neutrons rapides = New fuels for fast neutron reactorsLANGUILLE, A; MILLET, P; PILLON, S et al.Revue générale nucléaire. 1997, Num 3, pp 47-49, issn 0335-5004Article

Design concept of fast spectrum pulse reactor with packed core of coated dilute fuel particlesOBARA, T; SEKIMOTO, H.Journal of Nuclear Science and Technology. 1996, Vol 33, Num 7, pp 547-554, issn 0022-3131Article

Extraction of uranium nitride pellets during extraction of lead from brest reactor fuel-element simulators by meltingSUKHANOV, L. P; USTINOV, O. A; SOROKIN, V. I et al.Atomic energy (New York, N.Y.). 2005, Vol 99, Num 1, pp 514-517, issn 1063-4258, 4 p.Article

Electrochemical behaviors of PuN and (U, Pu)N in LiCl-KCl eutectic meltsSHIRAI, O; KATO, T; IWAI, T et al.The Journal of physics and chemistry of solids. 2005, Vol 66, Num 2-4, pp 456-460, issn 0022-3697, 5 p.Conference Paper

Nitrogen isotope separation by means of cation exchange resin. I: Effects of eluent concentrationOHTSUKA, H; OHWAKI, M; NOMURA, M et al.Journal of Nuclear Science and Technology. 1995, Vol 32, Num 10, pp 1001-1007, issn 0022-3131Article

Fabrication of (U, Pu)N fuel pelletsARAI, Y; FUKUSHIMA, S; SHIOZAWA, K et al.Journal of nuclear materials. 1989, Vol 168, Num 3, pp 280-289, issn 0022-3115Article

The closed on-site fuel cycle of the brest reactorsORLOV, V. V; FILIN, A. I; KARIMOV, R. S et al.Progress in nuclear energy (New series). 2005, Vol 47, Num 1-4, pp 171-177, issn 0149-1970, 7 p.Conference Paper

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