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...

Volume conservation during irradiation growth of Zr–2.5Nb

Journal of nuclear materials, 2004-12, Vol.335 (3), p.529-533

2004

Volltextzugriff (PDF)

Anisotropy of in-reactor deformation of Zr–2.5Nb pressure tubes

Journal of nuclear materials, 2003-05, Vol.317 (2), p.256-260

2003

Volltextzugriff (PDF)

In-reactor stress relaxation of selected metals and alloys at low temperatures

Journal of nuclear materials, 1980-05, Vol.90 (1), p.216-223

1980

Volltextzugriff (PDF)

The relation between stress-relaxation and creep for some zirconium alloys during neutron irradiation

Journal of nuclear materials, 1973-01, Vol.46 (3), p.281-292

1973

Volltextzugriff (PDF)

The effects of intergranular constraints on irradiation growth of Zircaloy-2 at 320 K

Journal of nuclear materials, 1987-11, Vol.150 (3), p.306-318

1987

Volltextzugriff (PDF)

Anisotropy of irradiation creep of Zr-2.5wt%Nb and Zircaloy-2 alloys

Journal of nuclear materials, 1981, Vol.98 (3), p.313-321

Causey, A.R.

1981

Volltextzugriff (PDF)

The effect of intergranular stresses on the texture dependence of irradiation growth in zirconium alloys

Journal of nuclear materials, 1988-10, Vol.159, p.225-236

1988

Volltextzugriff (PDF)

In-reactor creep of zircaloy-2, zircaloy-4 and Zr-1.15 wt % Cr-0.1 wt % Fe at 568 K derived from their stress-relaxation behaviour

Journal of nuclear materials, 1974, Vol.54 (1), p.64-72

Causey, A.R.

1974

Volltextzugriff (PDF)

Measurement of irradiation creep of zirconium alloys using stress relaxation

Journal of nuclear materials, 1988, Vol.159, p.101-113

1988

Volltextzugriff (PDF)

Acceleration of creep and growth of annealed zircaloy-4 by pre-irradiation to high fluences

Journal of nuclear materials, 1986-07, Vol.139 (3), p.277-278

1986

Volltextzugriff (PDF)

Thermally induced strain recovery in irradiated and unirradiated zirconium alloy stress-relaxation specimens

Journal of nuclear materials, 1976-01, Vol.61 (1), p.71-78

Causey, A.R.

1976

Volltextzugriff (PDF)

Factors Affecting Creep Sag of Fuel Channels in Candu-PHW Reactors

Canadian metallurgical quarterly, 1985-07, Vol.24 (3), p.207-214

1985

Volltextzugriff (PDF)

In-reactor oxidation of crevices and cracks in cold-worked Zr-2.5 wt% Nb

Journal of nuclear materials, 1977, Vol.71 (1), p.25-35

1977

Volltextzugriff (PDF)

In-reactor creep of zirconium-2.5 wt% niobium at 570 K

Journal of nuclear materials, 1976, Vol.60 (2), p.185-194

1976

Volltextzugriff (PDF)

Creep of single-crystal UO 2

Journal of nuclear materials, 1966, Vol.19 (1), p.42-49

1966

Volltextzugriff (PDF)

Microstructural changes during thermally induced strain recovery in irradiated zircaloy-4 stress relaxation specimens

Journal of nuclear materials, 1977-01, Vol.64 (3), p.308-312

1977

Volltextzugriff (PDF)

Measurement and analysis of the elongation of Zircaloy-2 pressure tubes in pickering generating station units 1 and 2

Nuclear engineering and design, 1980, Vol.58 (3), p.367-381

1980

Volltextzugriff (PDF)

Creep of single-crystal UO2

Journal of nuclear materials, 1966-01, Vol.19 (1), p.42-49

1966

Volltextzugriff (PDF)

Enhancing mummy ‘palaeobiographies’ through the use of multidisciplinary techniques and approaches

Journal of archaeological science, reports, 2023-02, Vol.47, p.103784, Article 103784

2023

Volltextzugriff (PDF)

Erosion and redeposition experiments in the pisces facility

Journal of nuclear materials, 1987-02, Vol.145, p.61-70

1987

Volltextzugriff (PDF)

DENGUE VIRUSES FROM FEBRILE PATIENTS IN NIGERIA, 1964-68

The Lancet (British edition), 1971, Vol.297 (7690), p.105-106

1971

Volltextzugriff (PDF)

1 – 21 von 21

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(21)
Mit Volltextzugriff
(20)

Publikationsform

Artikel
(21)

Sprache

Englisch
(21)

Erscheinungsjahr

n.n

Zeitschrift / Serie

3 weitere anzeigen...

Weniger anzeigen...

Menü

Weitere Dienste

Einstellungen

Volume conservation during irradiation growth of Zr–2.5Nb

Anisotropy of in-reactor deformation of Zr–2.5Nb pressure tubes

In-reactor stress relaxation of selected metals and alloys at low temperatures

The relation between stress-relaxation and creep for some zirconium alloys during neutron irradiation

The effects of intergranular constraints on irradiation growth of Zircaloy-2 at 320 K

Anisotropy of irradiation creep of Zr-2.5wt%Nb and Zircaloy-2 alloys

The effect of intergranular stresses on the texture dependence of irradiation growth in zirconium alloys

In-reactor creep of zircaloy-2, zircaloy-4 and Zr-1.15 wt % Cr-0.1 wt % Fe at 568 K derived from their stress-relaxation behaviour

Measurement of irradiation creep of zirconium alloys using stress relaxation

Acceleration of creep and growth of annealed zircaloy-4 by pre-irradiation to high fluences

Thermally induced strain recovery in irradiated and unirradiated zirconium alloy stress-relaxation specimens

Factors Affecting Creep Sag of Fuel Channels in Candu-PHW Reactors

In-reactor oxidation of crevices and cracks in cold-worked Zr-2.5 wt% Nb

In-reactor creep of zirconium-2.5 wt% niobium at 570 K

Creep of single-crystal UO 2

Microstructural changes during thermally induced strain recovery in irradiated zircaloy-4 stress relaxation specimens

Measurement and analysis of the elongation of Zircaloy-2 pressure tubes in pickering generating station units 1 and 2

Creep of single-crystal UO2

Enhancing mummy ‘palaeobiographies’ through the use of multidisciplinary techniques and approaches

Erosion and redeposition experiments in the pisces facility

DENGUE VIRUSES FROM FEBRILE PATIENTS IN NIGERIA, 1964-68

Suchergebnisse filtern