Inert matrix fuel for the utilisation of plutoniumLEDERGERBER, G; DEGUELDRE, C; HEIMGARTNER, P et al.Progress in nuclear energy (New series). 2001, Vol 38, Num 3-4, pp 301-308, issn 0149-1970Conference Paper

Preparation of uranium nitride in the form of microspheresLEDERGERBER, G; KOPAJTIC, Z; INGOLD, F et al.Journal of nuclear materials. 1992, Vol 188, pp 28-35, issn 0022-3115Conference Paper

Characterization and quality control of uranium-plutonium carbide for the AC-3/FFRF experimentLEDERGERBER, G; HERBST, R; ZWICKY, H. U et al.Journal of nuclear materials. 1988, Vol 153, pp 189-204, issn 0022-3115, 16 p.Conference Paper

Some aspects of the use of ZrN as an inert matrix for actinide fuelsBURGHARTZ, M; LEDERGERBER, G; HEIN, H et al.Journal of nuclear materials. 2001, Vol 288, Num 2-3, pp 233-236, issn 0022-3115Article

Preparation of transuranium fuel and target materials for the transmutation of actinides by gel coconversionLEDERGERBER, G; INGOLD, F; STRATTON, R. W et al.Nuclear technology. 1996, Vol 114, Num 2, pp 194-204, issn 0029-5450Article

Determination of trace element impurities in nuclear materials by inductively coupled plasma mass spectrometry in a glove-boxKOPAJTIC, Z; RÖLLIN, S; WERNLI, B et al.Journal of analytical atomic spectrometry (Print). 1995, Vol 10, Num 11, pp 947-953, issn 0267-9477Conference Paper

Corrosion product deposits on boiling-water reactor cladding: Experimental and theoretical investigation of magnetic propertiesORLOV, A; DEGUELDRE, C; WIESE, H et al.Journal of nuclear materials. 2011, Vol 416, Num 1-2, pp 117-124, issn 0022-3115, 8 p.Conference Paper

X-ray diffraction analysis and data interpretation of stabilized zirconia inert matrix fuel doped with plutoniumBURGHARTZ, M; LEDERGERBER, G; INGOLD, F et al.Progress in nuclear energy (New series). 2001, Vol 38, Num 3-4, pp 247-250, issn 0149-1970Conference Paper

Fuel fabrication processes, design and experimental conditions for the joint US-Swiss mixed carbide test in FFTF (AC-3 test)STRATTON, R. W; LEDERGERBER, G; INGOLD, F et al.Journal of nuclear materials. 1993, Vol 204, pp 39-49, issn 0022-3115Conference Paper

Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor latticeCHAWLA, R; GRIMM, P; HEIMGARTNER, P et al.Progress in nuclear energy (New series). 2001, Vol 38, Num 3-4, pp 359-362, issn 0149-1970Conference Paper

Measurement of the mechanical properties of thermally-shocked zirconia-based simulated inert matrix fuelLEE, Y.-W; KIM, H. S; KIM, S. H et al.Progress in nuclear energy (New series). 2001, Vol 38, Num 3-4, pp 231-236, issn 0149-1970Conference Paper

Preparation of simulated inert matrix fuel with different powders by dry milling methodLEE, Y.-W; KIM, H. S; KIM, S. H et al.Journal of nuclear materials. 1999, Vol 274, Num 1-2, pp 7-14, issn 0022-3115Conference Paper

AC-3-irradiation test of sphere-pac and pellet (U,Pu)C fuel in the US Fast Flux Test FacilityBART, G; BOTTA, F. B; HOTH, C. W et al.Journal of nuclear materials. 2008, Vol 376, Num 1, pp 47-59, issn 0022-3115, 13 p.Article

Behaviour of implanted xenon in yttria-stabilised zirconia as inert matrix of a nuclear fuelDEGUELDRE, C; POUCHON, M; DÖBELI, M et al.Journal of nuclear materials. 2001, Vol 289, Num 1-2, pp 115-121, issn 0022-3115Conference Paper

The irradiation test of Inert-Matrix Fuel in comparison to uranium plutonium mixed oxide fuel at the Halden ReactorKASEMEYER, U; HELLWIG, Ch; LEE, Y.-W et al.Progress in nuclear energy (New series). 2001, Vol 38, Num 3-4, pp 309-312, issn 0149-1970Conference Paper

Design study of an irradiation experiment with inert matrix and mixed-oxide fuel at the Halden boiling water reactorKASEMEYER, U; JOO, H.-K; LEDERGERBER, G et al.Journal of nuclear materials. 1999, Vol 274, Num 1-2, pp 160-166, issn 0022-3115Conference Paper