au.\*:("INFORUM GmbH")
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Jahrestagung Kerntechnik '95 = Annual Conference of Nuclear Engineering '95Nuclear engineering and design. 1997, Vol 170, Num 1-3, issn 0029-5493, 198 p.Conference Proceedings
Determining reliability parameters for personnel actions as a component in PSA for the Unterweser nuclear power stationOEHMGEN, T.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 133-146, issn 0029-5493Conference Paper
Cernavoda CANDU severe accident evaluationNEGUT, G; MARIN, A.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 67-72, issn 0029-5493Conference Paper
Introduction of a quality management system at the Gemeinschaftskernkraftwerk Neckar GMBH (GKN)HAUG, W; GRÄBER, U.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 21-25, issn 0029-5493Conference Paper
Nuclear criticality safety considerations for CASTOR casks with spent fuel of the Rossendorf nuclear devicesSEIFERT, E.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 53-58, issn 0029-5493Conference Paper
Back to the 'green field' : the experience and the results gained from the decommissioning of the Niederaichbach nuclear power plant (KKN)VALENCIA, L; PRECHTL, E.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 125-132, issn 0029-5493Conference Paper
Innovative fast breeder reactor concept 'RAPID' for improvement of reactor performance and proliferation resistanceKAMBE, M; UOTANI, M.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 9-19, issn 0029-5493Conference Paper
Modeling oxidic molten core-concrete interaction in WECHSLFOIT, J. J.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 73-79, issn 0029-5493Conference Paper
The integrated management system as an auxiliary means for providing data for the probabilistic safety assessmentKAHLERT, W; LÜTZOW, K.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 59-65, issn 0029-5493Conference Paper
Build-up of plutonium isotopes in HTR fuel elements: A comparison between computed prediction and chemical analysisWERNER, H.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 147-164, issn 0029-5493Conference Paper
Post test calculations to 11% break loca experiments on the integral test facility ISB-VVER using the thermalhydraulic code ATHLETKREPPER, E.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 3-7, issn 0029-5493Conference Paper
Calculation of BWR cycles with CASMO-3-MICROBURN-B and comparison with measurementsMISU, S; GRUMMER, R. G.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 183-191, issn 0029-5493Conference Paper
ASYNT-an adjoint synthesis method for neutron irradiation estimation on the vessels of VVER/PWR reactorsBELOUSOV, S. I; ILIEVA, K. D.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 27-33, issn 0029-5493Conference Paper
Analysis of a boron dilution accident for WWER-440 combining the use of the codes DYN3D and SiTapROHDE, U; ELKIN, I; KALINENKO, V et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 95-99, issn 0029-5493Conference Paper
Concept for monitoring gaseous and aerosol-bound radioactive discharges from boiling and pressurized water reactor plants in the event of design basis and severe accidentsSAAD, M; BERGER, E; RÖBIG, G et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 119-124, issn 0029-5493Conference Paper
Generation and validation of ORIGEN-S libraries for depletion and transmutation calculations based on JEF2.2 and EAF3 basic dataHOOGENBOOM, J. E; KLOOSTERMAN, J. L.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 107-118, issn 0029-5493Conference Paper
Experience with the dismantling of three secondary steam generators in unit A in Gundremmingen by the 'ice-sawing' techniqueSTEINER, H; EICKELPASCH, N; TEGETHOFF, H et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 165-173, issn 0029-5493Conference Paper
Design of a gadolinia bearing mixed-oxide fuel assembly for pressurized water reactorsYAMATE, K; MORI, M; USHIO, T et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 35-51, issn 0029-5493Conference Paper
The nuclear fuel cycle backend : The use of the CEA critical facilities for the assessment of the physicsCABRILLAT, J. C; CHAUVIN, J. P; MARTINI, M et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 89-93, issn 0029-5493Conference Paper
Influence of fuel bundle loading errors on the subcriticality during refueling campaigns for the present BWR cores of KRB-IIKECK, B; SEIBOLD, F; WOLF, R et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 101-106, issn 0029-5493Conference Paper
Reduced stress welding process for nuclear plant pipingCHAPMAN, T; OFFER, H; SANDERS, W et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 81-88, issn 0029-5493Conference Paper
The application of mechanical and thermal cutting tools for the dismantling of activated internals of the reactor pressure Vessels in the versuchsatomkraftwerk, Kahl and the Gundremmingen Unit AEICKELPASCH, N; KALWA, H; STEINER, H et al.Nuclear engineering and design. 1997, Vol 170, Num 1-3, pp 175-182, issn 0029-5493Conference Paper