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...

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

Journal of nuclear materials, 2008-10, Vol.381 (1), p.119-123

2008

Volltextzugriff (PDF)

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 °C in the target region of the high flux isotope reactor

Journal of nuclear materials, 2008-10, Vol.381 (1), p.114-118

2008

Volltextzugriff (PDF)

FMEA of marine systems: moving from prescriptive to risk-based design and classification

Annual Reliability and Maintainability Symposium. 2002 Proceedings (Cat. No.02CH37318), 2002, p.165-172

2002

Volltextzugriff (PDF)

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 deg C in the target region of the high flux isotope reactor

Journal of nuclear materials, 2008-10, Vol.381 (1-2), p.114-118

2008

Volltextzugriff (PDF)

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 °C in the target region of the high flux isotope reactor: Proceedings of the Seventh and Eighth International Graphite Specialists Meetings (INGSM)

Journal of nuclear materials, 2008, Vol.381 (1-2), p.114-118

2008

Volltextzugriff (PDF)

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor: Proceedings of the Seventh and Eighth International Graphite Specialists Meetings (INGSM)

Journal of nuclear materials, 2008, Vol.381 (1-2), p.119-123

2008

Volltextzugriff (PDF)

Prediction of the Local Pressure Gradient during Partially Developed Subcooled Boiling in Research Reactors of High Power Density

Nuclear science and engineering, 1997-02, Vol.125 (2), p.232-242

1997

Volltextzugriff (PDF)

Using quantitative analysis to make risk-based decisions

Annual Reliability and Maintainability Symposium, 2003, 2003, p.170-176

2003

Volltextzugriff (PDF)

Building a Self-Sustaining Psychology Research Team in Academic Medicine: A Multi-Tiered Mentorship Model

Journal of clinical psychology in medical settings, 2024-08

2024

Volltextzugriff (PDF)

Heat Shock Alters the Proteomic Profile of Equine Mesenchymal Stem Cells

International journal of molecular sciences, 2022-07, Vol.23 (13), p.7233

2022

Volltextzugriff (PDF)

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Nuclear Engineering and Technology, 2021, 53(3), , pp.920-926

2021

Volltextzugriff (PDF)

Psychophysiological effects of equine-facilitated psychotherapy on Veterans with PTSD and their horse partners

Journal of military, veteran and family health, 2024-06, Vol.10 (3), p.135-147

2024

Volltextzugriff (PDF)

The response of CR-39 nuclear track detector to 1-9 MeV protons

Review of scientific instruments, 2011-10, Vol.82 (10), p.103303-103303-7

2011

Volltextzugriff (PDF)

Health Disparities in Young Adults: A Direct Comparison of Distress and Unmet Needs Across Cancer Centers

JCO clinical cancer informatics, 2024-03 (8)

2024

Volltextzugriff (PDF)

Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO2 Test Targets for Improved Production

Nuclear technology, 2022-12, Vol.208, p.S18-S25

2022

Volltextzugriff (PDF)

Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO 2 Test Targets for Improved Production

Nuclear technology, 2022-12, Vol.208 (sup1), p.S18-S25

2022

Volltextzugriff (PDF)

Conceptual Design of HFIR Irradiation Experiment for Material Compatibility Study on Liquid Sn Divertor

Plasma and Fusion Research, 2021/05/07, Vol.16, pp.2405040-2405040

2021

Volltextzugriff (PDF)

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Nuclear engineering and technology, 2021, Vol.53 (3), p.920-926

2021

Volltextzugriff (PDF)

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Nuclear engineering and technology, 2020-08

2020

Volltextzugriff (PDF)

Selection and Validation of Reference Genes for Gene Expression Studies in an Equine Adipose-Derived Mesenchymal Stem Cell Differentiation Model by Proteome Analysis and Reverse-Transcriptase Quantitative Real-Time PCR

Genes, 2023-03, Vol.14 (3), p.673

2023

Volltextzugriff (PDF)

Erratum: “The response of CR-39 nuclear track detector to 1–9 MeV protons” [Rev. Sci. Instrum. 82, 103303 (2011)]

Review of scientific instruments, 2014-11, Vol.85 (11)

2014

Volltextzugriff (PDF)

Proteins containing non-native disulfide bonds generated by oxidative stress can act as signals for the induction of the heat shock response

Journal of cellular physiology, 1997-05, Vol.171 (2), p.143-151

1997

Volltextzugriff (PDF)

An accelerator based fusion-product source for development of inertial confinement fusion nuclear diagnostics

Review of scientific instruments, 2008-04, Vol.79 (4), p.043302-043302-6

2008

Volltextzugriff (PDF)

Compact multichannel neutral particle analyzer for measurement of energetic charge-exchanged neutrals in Alcator C-Mod

Review of scientific instruments, 2006-08, Vol.77 (8)

2006

Volltextzugriff (PDF)

The response of CR-39 nuclear track detector to 1-9 MeV protons

Review of scientific instruments, 2011-10, Vol.82 (10)

2011

Volltextzugriff (PDF)

1 – 25 von 41

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(36)
Mit Volltextzugriff
(34)

Publikationsform

Sprache

Englisch
(39)
Koreanisch
(1)

Erscheinungsjahr

n.n

Thema

15 weitere anzeigen...

Weniger anzeigen...

Neu hinzugefügt

... seit 90 Tagen
(1)

Menü

Weitere Dienste

Einstellungen

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 °C in the target region of the high flux isotope reactor

FMEA of marine systems: moving from prescriptive to risk-based design and classification

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 deg C in the target region of the high flux isotope reactor

Experimental plan and design of two experiments for graphite irradiation at temperatures up to 1500 °C in the target region of the high flux isotope reactor: Proceedings of the Seventh and Eighth International Graphite Specialists Meetings (INGSM)

Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor: Proceedings of the Seventh and Eighth International Graphite Specialists Meetings (INGSM)

Prediction of the Local Pressure Gradient during Partially Developed Subcooled Boiling in Research Reactors of High Power Density

Using quantitative analysis to make risk-based decisions

Building a Self-Sustaining Psychology Research Team in Academic Medicine: A Multi-Tiered Mentorship Model

Heat Shock Alters the Proteomic Profile of Equine Mesenchymal Stem Cells

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Psychophysiological effects of equine-facilitated psychotherapy on Veterans with PTSD and their horse partners

The response of CR-39 nuclear track detector to 1-9 MeV protons

Health Disparities in Young Adults: A Direct Comparison of Distress and Unmet Needs Across Cancer Centers

Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO2 Test Targets for Improved Production

Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO 2 Test Targets for Improved Production

Conceptual Design of HFIR Irradiation Experiment for Material Compatibility Study on Liquid Sn Divertor

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Selection and Validation of Reference Genes for Gene Expression Studies in an Equine Adipose-Derived Mesenchymal Stem Cell Differentiation Model by Proteome Analysis and Reverse-Transcriptase Quantitative Real-Time PCR

Erratum: “The response of CR-39 nuclear track detector to 1–9 MeV protons” [Rev. Sci. Instrum. 82, 103303 (2011)]

Proteins containing non-native disulfide bonds generated by oxidative stress can act as signals for the induction of the heat shock response

An accelerator based fusion-product source for development of inertial confinement fusion nuclear diagnostics

Compact multichannel neutral particle analyzer for measurement of energetic charge-exchanged neutrals in Alcator C-Mod

The response of CR-39 nuclear track detector to 1-9 MeV protons

Suchergebnisse filtern