UB Paderborn / Katalog / Suche / in CDI

1 – 25 von 105

Sortiert nach

Comparative Analysis on Fuel Breeding for Less Moderation Ratio of Water Cooled Reactor

Journal of physics. Conference series, 2019-04, Vol.1204 (1), p.12129

2019

Link zum Volltext

Verfügbarkeit prüfen

Low-Cost Sensor Deployment on a Public Minibus in Fukushima Prefecture

Sensors (Basel, Switzerland), 2024-02, Vol.24 (5), p.1375

2024

Link zum Volltext

Verfügbarkeit prüfen

Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel

Nuclear science and techniques, 2022-12, Vol.33 (12), p.173-189, Article 165

2022

Link zum Volltext

Verfügbarkeit prüfen

Nitrate salt phase transition study for molten salt loop working fluid consideration

Heat and mass transfer, 2024, Vol.60 (1), p.117-132

2024

Link zum Volltext

Verfügbarkeit prüfen

Basic design analysis of a heavy water-cooled thorium breeder reactor

Nuclear engineering and design, 2020-08, Vol.364, p.110689, Article 110689

Permana, Sidik

2020

Link zum Volltext

Verfügbarkeit prüfen

Basic design parameter optimization on water cooled thorium breeder reactor

Annals of nuclear energy, 2020-05, Vol.139, p.107218, Article 107218

Permana, Sidik

2020

Link zum Volltext

Verfügbarkeit prüfen

Analysis on different material attractiveness concept based on plutonium composition of FBR blanket system

Progress in nuclear energy (New series), 2020-09, Vol.127, p.103404, Article 103404

Permana, Sidik

2020

Link zum Volltext

Verfügbarkeit prüfen

Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant

Nuclear engineering and technology, 2021-02, Vol.53 (2), p.423-429

2021

Link zum Volltext

Verfügbarkeit prüfen

Magnetic field analysis of shimmed DECY-13 cyclotron magnet

AIP Conference Proceedings, 2021, Vol.2381 (1)

2021

Link zum Volltext

Verfügbarkeit prüfen

Filtration efficiency analysis of cotton cloth-based mask for reducing transmission rate of COVID-19 using PM2.5 detection methods

Journal of physics. Conference series, 2022-06, Vol.2243 (1), p.12067

2022

Link zum Volltext

Verfügbarkeit prüfen

Thorium Fuel Utilization Analysis on Small Long Life Reactor for Different Coolant Types

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12060

Permana, Sidik

2017

Link zum Volltext

Verfügbarkeit prüfen

Fuel Sustainability And Actinide Production Of Doping Minor Actinide In Water-Cooled Thorium Reactor

Journal of physics. Conference series, 2017-07, Vol.877 (1), p.12019

Permana, Sidik

2017

Link zum Volltext

Verfügbarkeit prüfen

Experimental and simulation approach of the loop geometry effect on the natural circulation system of the advanced nuclear reactor

International journal of energy research, 2021-06, Vol.45 (8), p.11892-11903

2021

Link zum Volltext

Verfügbarkeit prüfen

Thermalhydraulic calculation for boiling water reactor and its natural circulation component

AIP Conference Proceedings, 2015, Vol.1677 (1)

2015

Link zum Volltext

Verfügbarkeit prüfen

Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping

AIP Conference Proceedings, 2014, Vol.1615 (1), p.56

2014

Link zum Volltext

Verfügbarkeit prüfen

Analysis on burnup step effect for evaluating reactor criticality and fuel breeding ratio

AIP Conference Proceedings, 2014, Vol.1615 (1), p.90

2014

Link zum Volltext

Verfügbarkeit prüfen

Design Conceptual of 800MWt Long Life Pressurized Water Reactor Using (Th-U)O2 Fuels with Gd2O3 and Pa-231 as Burnable Poisons

Journal of physics. Conference series, 2020-03, Vol.1493 (1)

2020

Link zum Volltext

Verfügbarkeit prüfen

Design Conceptual of 800MWt Long Life Pressurized Water Reactor Using (Th-U)O 2 Fuels with Gd 2 O 3 and Pa-231 as Burnable Poisons

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12006

2020

Link zum Volltext

Verfügbarkeit prüfen

Conceptual design study of small long-life PWR based on thorium cycle fuel

AIP Conference Proceedings, 2014, Vol.1615 (1), p.64

2014

Link zum Volltext

Verfügbarkeit prüfen

Evaluated Material Attractiveness of Plutonium Composition from Economic Simplified Boiling Water Reactor (ESBWR)

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12058

2024

Link zum Volltext

Verfügbarkeit prüfen

Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006

Journal of physics. Conference series, 2024-03, Vol.2734 (1), p.12057

2024

Link zum Volltext

Verfügbarkeit prüfen

Nuclear Energy Contribution for Net Zero Emission and National Energy Mix 2060 in Indonesia

Journal of physics. Conference series, 2022-06, Vol.2243 (1), p.12066

2022

Link zum Volltext

Verfügbarkeit prüfen

Design and validation of a single cylindrical neutron spectrometer using a gold activation foil

Radiation measurements, 2024-02, Vol.171, p.107053, Article 107053

2024

Link zum Volltext

Verfügbarkeit prüfen

Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle

Nuclear engineering and design, 2024-03, Vol.418, p.112934, Article 112934

2024

Link zum Volltext

Verfügbarkeit prüfen

Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel

Nuclear engineering and design, 2023-12, Vol.414, p.112646, Article 112646

2023

Link zum Volltext

Verfügbarkeit prüfen

1 – 25 von 105

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(96)
Mit Volltextzugriff
(86)

Publikationsform

Artikel
(87)
Tagungsberichte
(18)

Sprache

Erscheinungsjahr

n.n

Thema

15 weitere anzeigen...

Weniger anzeigen...

Neu hinzugefügt

... seit 90 Tagen
(3)

Menü

Weitere Dienste

Einstellungen

Comparative Analysis on Fuel Breeding for Less Moderation Ratio of Water Cooled Reactor

Low-Cost Sensor Deployment on a Public Minibus in Fukushima Prefecture

Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel

Nitrate salt phase transition study for molten salt loop working fluid consideration

Basic design analysis of a heavy water-cooled thorium breeder reactor

Basic design parameter optimization on water cooled thorium breeder reactor

Analysis on different material attractiveness concept based on plutonium composition of FBR blanket system

Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant

Magnetic field analysis of shimmed DECY-13 cyclotron magnet

Filtration efficiency analysis of cotton cloth-based mask for reducing transmission rate of COVID-19 using PM2.5 detection methods

Thorium Fuel Utilization Analysis on Small Long Life Reactor for Different Coolant Types

Fuel Sustainability And Actinide Production Of Doping Minor Actinide In Water-Cooled Thorium Reactor

Experimental and simulation approach of the loop geometry effect on the natural circulation system of the advanced nuclear reactor

Thermalhydraulic calculation for boiling water reactor and its natural circulation component

Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping

Analysis on burnup step effect for evaluating reactor criticality and fuel breeding ratio

Design Conceptual of 800MWt Long Life Pressurized Water Reactor Using (Th-U)O2 Fuels with Gd2O3 and Pa-231 as Burnable Poisons

Design Conceptual of 800MWt Long Life Pressurized Water Reactor Using (Th-U)O 2 Fuels with Gd 2 O 3 and Pa-231 as Burnable Poisons

Conceptual design study of small long-life PWR based on thorium cycle fuel

Evaluated Material Attractiveness of Plutonium Composition from Economic Simplified Boiling Water Reactor (ESBWR)

Neutronic and Proliferation Resistance Analysis of Small Modular Pressurized Water Reactor with Various Fuel Types using SRAC 2006

Nuclear Energy Contribution for Net Zero Emission and National Energy Mix 2060 in Indonesia

Design and validation of a single cylindrical neutron spectrometer using a gold activation foil

Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle

Neutronic design performance of 100 MWe MSR with thorium-enriched uranium and thorium-plutonium-minor actinide fuel

Suchergebnisse filtern