81
Systemanalyse Mischkonzept: Abschlussbericht technischer Anhang. 0001: Planung der Tagesanlagen.
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Systemanalyse Mischkonzept: Abschlussbericht technischer Anhang. 0004: Strahlenschutz im Endlager.
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Safety of the nuclear fuel cycle /
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Ebert, K.
1989
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84
Computer Tomographie an Fässern mit radioaktivem Inhalt [E-Book] /
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Radioactive waste forms for the future /
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86
Radiation protection in nuclear energy. vol 0002 : International conference on radiation protection in nuclear energy: proceedings : Sidney, 18.04.88-22.04.88
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1988
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APCA annual meeting. 81: proceedings. 2 : Dallas, TX, 19.06.88-24.06.88
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1988
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88
The regulatory framework for storage and disposal of radioactive waste in the member states of the European Community.
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89
Waste management. 1988: waste processing, transportation, storage and disposal technical programs and public education. vol 1 : Symposium on waste management : Tucson, AZ, 28.02.88-03.03.88.
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Waste management 1988: waste processing, transportation, storage and disposal technical programs and public education. vol 2 : Symposium on Waste Management : Tucson, AZ, 28.02.88-03.03.88.
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Survey of experience with dry storage of spent nuclear fuel and update of wet storage experience.
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1988
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92
NEA Workshop on Near Field Assessment of Repositories for Low and Medium Level Radioactive Waste: proceedings : Reunion de travail de l' AEN sur l' evaluation du champ proche des depots de dechets radioactifs de faible et moyenne activite: compte rendu : Baden, 23.11.87-25.11.87.
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1988
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Ableitung von Aktivitätsgrenzwerten für schwach radioaktiv kontaminierte Abfälle.
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Bericht der Bundesregierung an den Deutschen Bundestag zur Entsorgung der Kernkraftwerke und anderer kerntechnischer Einrichtungen.
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1988
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Joint German Indonesian seminar on public acceptance, waste management, and nuclear safety, Jakarta October 7 - 9, 1986 [E-Book]
1988
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Untersuchungen zur Vermeidung der Bildung von Radiolyse Wasserstoff in 200 Liter Fässern mit zementiertem wärmeentwickelndem MAW aus der WAK [E-Book] /
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Massenenergieabsorbtionskoeffizienten im Bereich von 15 KeV bis 3.5 MeV und Dosisleistungsaufbaukoeffizienten A1, -A1 und A2 im Bereich von 0.28 MeV bis 3.5 MeV für Beton: eine tabellarische Bearbeitung der Werte in Schritten von 500 EV und 1 KeV [E-Book] /
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Seminar Entsorgung radioaktiver Abfälle : Jülich, 14. und 15. Juni 1988 [E-Book] /
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Management and disposal of spent nuclear fuel : review of a programme for research, development, and other measures /
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1987
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Proceedings of an NEA Workshop on Uncertainty Analysis for Performance Assessments of Radioactive Waste Disposal Systems : Seattle, United States, 24-26 February 1987 /
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1987
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