21
KONWAR : eine Erweiterung von ATHLET zur Berechnung der Kondensation in waagerechten Rohren [E-Book] /
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Nachinertisierung von Reaktor-Sicherheitsbehältern durch Einspeisung von flüssigem Kohlendioxid /
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Guidebook on destructive examination of water reactor fuel /
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1997
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Allgemeine Beschreibung des NOKO Versuchsstandes [E-Book] /
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Experimentelle und analytische Untersuchungen zur Wirksamkeit des Notkondensators des SWR600/1000 [E-Book]/
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26
Selected safety aspects of WWER 440 model 213 nuclear power plants: final report of the IAEA project on evaluation of safety aspects for WWER 440 model 213 nuclear power plants: reference plant: Bohunice NPP V2 (Slovakia)
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1996
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Beitrag zur Charakterisierung von Oxidschichten auf dem Stahl X6CrNiTi18 10 in wässrigen Elektrolyten bis 250 Grad Celsius und unter dem Einfluss von korrosionsinduzierenden und korrosionsinhibierenden Spezies.
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Tschernobyl - 10 Jahre danach: der Unfall und die Sicherheit der RBMK Anlagen.
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1996
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Design and performance of WWER fuel.
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1996
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Conference SFEN/KTA sur le projet EPR (European pressurized water reactor) : SFEN/KTG conference on the EPR (European pressurized water reactor) project : Strasbourg, 13.11.95-14.11.95.
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1995
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Erarbeitung von Unterlagen im Hinblick auf die Ergänzung und Weiterentwicklung des kerntechnischen Regelwerkes. Technischer Bericht 6. Einfluss ionisierender Strahlung auf das Korrosionsverhalten von austenitischen CrNi Stählen in LWR Medien.
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Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension : [papers presented at the symposium of the same name held in New Orleans, Louisiana, on 29-31 Jan. 1992] /
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Coolant technology of water cooled reactors : an overview.
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1993
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International Symposium on environmental degradation of materials in nuclear power systems - water reactors. 0004: proceedings : Jekyll-Island, GA, 06.08.89-10.08.89.
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Advanced water cooled reactor technologies : Rationale, state of progress and outlook.
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1989
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Review of fuel element developments for water cooled nuclear power reactors : International symposium on improvements in water reactor fuel technology and utilization : Stockholm, 15.09.86-19.09.86.
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1989
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Program of research and development on the thorium utilization in pwrs 1979 - 1988 : Final report [E-Book] /
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OECD Halden Reactor Project, 1958-1988.
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1988
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Heat transfer analysis of the existing HEU and proposed LEU cores of Pakistan research reactor [E-Book] /
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Sichtung und Bewertung von Unterlagen im Hinblick auf sicherheitstechnisch relevante Probleme und deren Berücksichtigung bei der Weiterentwicklung des kerntechnischen Regelwerks. Technischer Bericht 6. Beitrag zum derzeitigen Kenntnisstand über die dehnungsinduzierte Risskorrosion in druckführenden Komponenten aus ferritischen Werkstoffen (Schwerpunkt Siedwasserreaktoren)
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Deimel, P.
1987
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