Application of mercury porosimetry to powder (UO₂) analysisEMERUWA, E; JARRIGE, J; MEXMAIN, J et al.Journal of nuclear materials. 1991, Vol 184, Num 1, pp 53-58, issn 0022-3115Article

Foundations for the definition of MOX fuel quality requirementsBAIRIOT, H; DERAMAIX, P; MOSTIN, N et al.Journal of nuclear materials. 1991, Vol 178, Num 2-3, pp 187-194, issn 0022-3115Conference Paper

Prepatation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pelletsGANGULY, C; HEGDE, P. V; SENGUPTA, A. K et al.Journal of nuclear materials. 1991, Vol 178, Num 2-3, pp 234-241, issn 0022-3115Conference Paper

UO₂-Gd₂O₃ solid solution formation from wet and dry processesRIELLA, H. G; DURAZZO, M; HIRATA, M et al.Journal of nuclear materials. 1991, Vol 178, Num 2-3, pp 204-211, issn 0022-3115Conference Paper

Dry casks: an interim fuel storage solutionHALLS, R. L. SR; ROUTH, S. D; CARR, R. K et al.Power engineering (Barrington, IL.). 1987, Vol 91, Num 2, pp 34-38, issn 0032-5961Article

A demonstration facility for the IFR fuel cycleLINEBERRY, M. J; PHIPPS, R. D.International conference on nuclear fuel reprocessing and waste management. 1987, pp 153-160Conference Paper

Advanced separation processes for spent fuel reprocessing Italian experienceCANDELIERE, T; GASPARINI, G. M; GROSSI, G et al.International symposium on the back end of the nuclear fuel cycle: strategies and options. 1987, pp 475-481Conference Paper

Chemical investigations relevant to plutonium recyclingSOOD, D. D.International symposium on the back end of the nuclear fuel cycle: strategies and options. 1987, pp 561-562Conference Paper

Decadal operational experience of the Tokai reprocessing plantYAMANOUCHI, T; OMACHI, S; MATSUMOTO, K et al.International conference on nuclear fuel reprocessing and waste management. 1987, pp 195-202Conference Paper

Development of FBR fuel reprocessing technology in PNCSASAO, N; HAYASHI, S; KISHIMOTO, Y et al.International conference on nuclear fuel reprocessing and waste management. 1987, pp 161-168Conference Paper

IAEA-SM294/7P. Potential for Np and Am recyclingKOCH, L.International symposium on the back end of the nuclear fuel cycle: strategies and options. 1987, pp 551-553Conference Paper

Lessons from La Hague on process chemistry in LWR spent fuel reprocessingPATIGNY, P; PAGERON, D; SALOM, J et al.International conference on nuclear fuel reprocessing and waste management. 1987, pp 403-410Conference Paper

Results and objectives of R & D work for nuclear fuel reprocessingSCHMIEDER, H; BLEYL, H.-J; GALLA, U et al.International conference on nuclear fuel reprocessing and waste management. 1987, pp 393-402Conference Paper

Simulation of the chopping of irradiated PWR ROD bundlesCOLAS, J; PELLIER, R; PHILIPPE, M et al.International conference on nuclear fuel reprocessing and waste management. 1987, pp 1463-1470Conference Paper

Aspects économiques du recyclage du plutonium dans les REP = Economic aspects of plutonium recycling in PWRsBAUMIER, J.International symposium on the back end of the nuclear fuel cycle: strategies and options. 1987, pp 529-540Conference Paper

Le combustible au plutonium de Fragema dans les REP = Fragema's plutonium fuel in PWRsCASTELLI, R; CHOTARD, A; MOURLEVAT, J.-L et al.International symposium on the back end of the nuclear fuel cycle: strategies and options. 1987, pp 558-561Conference Paper

L'enrichissement au Tricastin: les raisons d'une bonne santé = Enrichment at Tricastin: the reasons for successÉnergie magazine. 1986, Num 83-84, pp 32-33, issn 0755-5202Article

Exxon Nuclear modernise l'usine de Lingen = Exxon Nuclear is modernizing Lingen plantÉnergie magazine. 1986, Num 82, issn 0755-5202, 58Article

Uranium Pechiney dans le cycle du combustible = Uranium Pechiney in the fuel cycleLIEGEOIS, E.Énergie nucléaire magazine. 1984, Num 7, pp 25-30, issn 0755-5350Article

Derivation of uncertainties to be used with the MONKS code for water moderated, low enriched uranium systemsCHESTNVTT, M. M; HILL, E. A.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 398-446Conference Paper

Description of experiments on low enriched uranium oxide powder at low moderationMA TERTON, E; SHERWIN, J; SMALL, G et al.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 384-397Conference Paper

Kinetics calculationsSEALE, R. L.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 300-341Conference Paper

Rockwell International's critical mass laboratory program at the Rocky Flats PlantMCCARTHY, J. D.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 252-257Conference Paper

Caractéristiques de l'ensemble de détection français des accidents de criticité (système EDAC) = The characteristics of the French detection system of criticality accidents (EDAC system)BARBRY, F; PRIGENT, R.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 13-27Conference Paper

Les expériences CRISTO III: études de l'effet du gadolinium sous forme soluble dans des réseaux à eau ordinaire = CRISTO III experiments: study of the effect of gadolinium under soluble form in light water latticesDARROUZET, M; EL IDRISSI, N; SANTAMARINA, A et al.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 100-126Conference Paper