UB Paderborn / Katalog / Suche / in CDI

Sortiert nach

Einfacher Volltextzugriff von (fast) überall

Installieren Sie die LibKey Nomad-Browsererweiterung und erhalten Sie von vielen Webseiten einfachen Zugriff auf lizenzierte Volltexte oder Open Access Publikationen. Mehr erfahren...

Selection of Nuclear Safety and Its Deployment

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1998/02/28, Vol.40(2), pp.101-110

TAKETANI, Kiyoaki

1998

Volltextzugriff (PDF)

A Proposal for Japanese Nuclear Sterategy

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1995/04/28, Vol.37(4), pp.283-290

TAKETANI, Kiyoaki

1995

Volltextzugriff (PDF)

Nuclear safety and its deployment for human beings

Nuclear engineering and design, 1992-08, Vol.136 (1), p.29-34

Taketani, Kiyoaki

1992

Volltextzugriff (PDF)

Small and Medium Sized Reactors and Its Recent Foreign Response among Countries

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1988/05/30, Vol.30(5), pp.400-409

TAKETANI, Kiyoaki

1988

Volltextzugriff (PDF)

Void Migration in Sodium Chloride Crystal under Temperature Gradient

Journal of nuclear science and technology, 1969-02, Vol.6 (2), p.55-62

1969

Volltextzugriff (PDF)

Xe Release from UO2 upon Oxidation

Journal of nuclear science and technology, 1969-06, Vol.6 (6), p.346-347

1969

Volltextzugriff (PDF)

Release of Xenon from Sintered UO2 at Low Temperatures

Journal of nuclear science and technology, 1967-12, Vol.4 (12), p.589-594

1967

Volltextzugriff (PDF)

On the Microstructure of UO2 Pellets Irradiated at High Temperature

Journal of nuclear science and technology, 1967-01, Vol.4 (1), p.1-10

1967

Volltextzugriff (PDF)

Oxidation of Uranium by Partially Decomposed Carbon Dioxide: Study on the Behavior of Punctured Fuel Element for Calder Hall Type Reactor, (5)

Journal of nuclear science and technology, 1965-07, Vol.2 (7), p.241-244

1965

Volltextzugriff (PDF)

Diffusion Coefficient of Fission Gas in Uranium Dioxide Powder Formed by Carbon Dioxide Oxidation of Uranium: Study on the Behavior of a Punctured Fuel Element for Calder-Hall Type Reactor, (4)

Journal of nuclear science and technology, 1965-06, Vol.2 (6), p.212-216

1965

Volltextzugriff (PDF)

Measurement of Fine Pores in Sintered UO2 by Krypton Adsorption

Journal of nuclear science and technology, 1965-06, Vol.2 (6), p.237-238

1965

Volltextzugriff (PDF)

Fission Gas Release from Uranium Heated in Carbon Dioxide: Study on the Behavior of Punctured Fuel Element for Calder Hall Type Reactor, (3)

Journal of nuclear science and technology, 1965-05, Vol.2 (5), p.168-171

1965

Volltextzugriff (PDF)

Fuel Irradiation Research and Development in Japan

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1967/02/28, Vol.9(2), pp.72-82

TAKETANI, Kiyoaki

1967

Volltextzugriff (PDF)

Room Temperature Oxidation of UN Powder

Journal of nuclear science and technology, 1970, Vol.7 (9), p.433-438

1970

Volltextzugriff (PDF)

Detection of Methyl Iodide upon Heating Irradiated Fuels

Journal of nuclear science and technology, 1968-10, Vol.5 (10), p.491-497

1968

Volltextzugriff (PDF)

The Behavior of the Crystals and the Voids in Centrally Heated UO2 Green Pellets

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1966/05/30, Vol.8(5), pp.248-256

TAKETANI, Kiyoaki

1966

Volltextzugriff (PDF)

On the Hot Metallurgy Laboratory in JAERI, (I): Study for fuel development, (8)

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1961/12/30, Vol.3(12), pp.929-935

TAKETANI, Kiyoaki

1961

Volltextzugriff (PDF)

Uranium Dioxide Fuel Pin Elongation Behavior under Irradiation

Journal of nuclear science and technology, 1971-09, Vol.8 (9), p.528-530

1971

Volltextzugriff (PDF)

Segregation of Fission Products in Natural UO2 Pellets Irradiated at High Temperature

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1968/08/30, Vol.10(8), pp.426-434

1968

Volltextzugriff (PDF)

Irradiation of Natural UO2 Pellets

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1967/08/30, Vol.9(8), pp.447-454

1967

Volltextzugriff (PDF)

Oxidation Rate of Intentionally Punctured Dummy Fuel Element: Study on the behavior of punctured fuel element for Calder Hall type reactor, (2)

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1963/06/30, Vol.5(6), pp.481-491

1963

Volltextzugriff (PDF)

Observation of Oxidation of Intentionally Punctured Dummy Fuel Element: Study on the behavior of punctured fuel element for Calder-Hall type reactor, (1)

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1963/04/30, Vol.5(4), pp.310-315

1963

Volltextzugriff (PDF)

Study on the Thermal Cycling Effect of Uranium by X-ray Inverse Pole Figure Method, (I): Study on uranium fuel element, (7)

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1960/07/30, Vol.2(7), pp.406-411

1960

Volltextzugriff (PDF)

ON THE AGE-HARDENABLE AND CORROSION-RESISTANT Al-Mg-Si TERNARY ALLOYS

Keikinzoku, 1953, Vol.1953 (6), p.56-62

1953

Volltextzugriff (PDF)

On the Hot Metallurgy Laboratory in JAERI, (I)

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1961, Vol.3 (12), p.929-935

TAKETANI, Kiyoaki

1961

Volltextzugriff (PDF)

1 – 25 von 40

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(21)
Mit Volltextzugriff
(39)

Publikationsform

Artikel
(40)

Sprache

Englisch
(28)
Japanisch
(19)

Erscheinungsjahr

n.n

Thema

15 weitere anzeigen...

Weniger anzeigen...

Kollektion

3 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

Selection of Nuclear Safety and Its Deployment

A Proposal for Japanese Nuclear Sterategy

Nuclear safety and its deployment for human beings

Small and Medium Sized Reactors and Its Recent Foreign Response among Countries

Void Migration in Sodium Chloride Crystal under Temperature Gradient

Xe Release from UO2 upon Oxidation

Release of Xenon from Sintered UO2 at Low Temperatures

On the Microstructure of UO2 Pellets Irradiated at High Temperature

Oxidation of Uranium by Partially Decomposed Carbon Dioxide: Study on the Behavior of Punctured Fuel Element for Calder Hall Type Reactor, (5)

Diffusion Coefficient of Fission Gas in Uranium Dioxide Powder Formed by Carbon Dioxide Oxidation of Uranium: Study on the Behavior of a Punctured Fuel Element for Calder-Hall Type Reactor, (4)

Measurement of Fine Pores in Sintered UO2 by Krypton Adsorption

Fission Gas Release from Uranium Heated in Carbon Dioxide: Study on the Behavior of Punctured Fuel Element for Calder Hall Type Reactor, (3)

Fuel Irradiation Research and Development in Japan

Room Temperature Oxidation of UN Powder

Detection of Methyl Iodide upon Heating Irradiated Fuels

The Behavior of the Crystals and the Voids in Centrally Heated UO2 Green Pellets

On the Hot Metallurgy Laboratory in JAERI, (I): Study for fuel development, (8)

Uranium Dioxide Fuel Pin Elongation Behavior under Irradiation

Segregation of Fission Products in Natural UO2 Pellets Irradiated at High Temperature

Irradiation of Natural UO2 Pellets

Oxidation Rate of Intentionally Punctured Dummy Fuel Element: Study on the behavior of punctured fuel element for Calder Hall type reactor, (2)

Observation of Oxidation of Intentionally Punctured Dummy Fuel Element: Study on the behavior of punctured fuel element for Calder-Hall type reactor, (1)

Study on the Thermal Cycling Effect of Uranium by X-ray Inverse Pole Figure Method, (I): Study on uranium fuel element, (7)

ON THE AGE-HARDENABLE AND CORROSION-RESISTANT Al-Mg-Si TERNARY ALLOYS

On the Hot Metallurgy Laboratory in JAERI, (I)

Suchergebnisse filtern