UB Paderborn / Katalog / Suche / in CDI

1 – 25 von 560

Sortiert nach

Equilibrium Core Design of Reaktor Daya Eksperimental

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22076

2019

Link zum Volltext

Verfügbarkeit prüfen

Safety assessment of pressure vessel components for Reaktor Daya Eksperimental

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12023

2020

Link zum Volltext

Verfügbarkeit prüfen

Semi-Analytical Methods and Simulation for Temperature Distribution of Helium Purification System for Reaktor Daya Eksperimental

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12040

2021

Link zum Volltext

Verfügbarkeit prüfen

R&D on Surrogate Kernel Fabrication in Support of Reaktor Daya Eksperimental (RDE) Project

Journal of physics. Conference series, 2021-10, Vol.2048 (1), p.12011

2021

Link zum Volltext

Verfügbarkeit prüfen

Preliminary Development of the FPGA based Reactor Protection Systems for Reaktor Daya Eksperimental (RDE)

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12045

2021

Link zum Volltext

Verfügbarkeit prüfen

Considerations of Material Selection for Control Rod Drive Mechanism of Reaktor Daya Eksperimental

Journal of physics. Conference series, 2019-04, Vol.1198 (3), p.32010

2019

Link zum Volltext

Verfügbarkeit prüfen

Sensitivity of heat transfer parameters on the Reaktor Daya Eksperimental - RDE core

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22049

2019

Link zum Volltext

Verfügbarkeit prüfen

Investigation of graphite matrix activation in the fuel pebble of Reaktor Daya Eskperimental

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22021

2019

Link zum Volltext

Verfügbarkeit prüfen

Study of structure systems and components classification of Reaktor Daya Eksperimental - RDE based on life cycle management

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22048

2019

Link zum Volltext

Verfügbarkeit prüfen

Modeling of BN-600 Hybrid Core Benchmark (HEX-Z) with MCU-PTR and SERPENT 2

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12046

2020

Link zum Volltext

Verfügbarkeit prüfen

To estimate reliability of hydroaccumulator system of nuclear power plants and improve its design and reliability

Journal of physics. Conference series, 2020-11, Vol.1701 (1), p.12002

2020

Link zum Volltext

Verfügbarkeit prüfen

Physical aspects for involvement of thermonuclear reactors into nuclear power systems

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12033

2020

Link zum Volltext

Verfügbarkeit prüfen

Possibilities and Features of REMIX Technology as an Initial Stage in the Establishing of a Full-Scale Two-Component Nuclear Energy System

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12010

2020

Link zum Volltext

Verfügbarkeit prüfen

Preliminary Development of Online Remote Multipurpose Reactor Monitoring System

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12043

2021

Link zum Volltext

Verfügbarkeit prüfen

The main problems of transmutation of actinides and long-lived fission products from NPP spent fuel

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12032

2020

Link zum Volltext

Verfügbarkeit prüfen

Possible ways to solve the problems of using MOX fuel in thermal reactors

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12036

2020

Link zum Volltext

Verfügbarkeit prüfen

Investigation of radiation levels in the region of fuel-transfer cask for transportation of spent fuel of light-water reactors

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12070

2020

Link zum Volltext

Verfügbarkeit prüfen

Analysis of the connection of an idle MCP with three operating without a preliminary reduction in the power of the VVER-1000 reactor

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12044

2020

Link zum Volltext

Verfügbarkeit prüfen

Role of fast sodium reactors in closure of the nuclear fuel cycle in the nuclear power system

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12005

2020

Link zum Volltext

Verfügbarkeit prüfen

Program for CNFC R&D using BN-800

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12020

2020

Link zum Volltext

Verfügbarkeit prüfen

Modeling the core of a lead-cooled reactor

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12052

2020

Link zum Volltext

Verfügbarkeit prüfen

Research study of possibility producing radioisotope Mo-99 in the active core of the BN-600 reactor using an irradiated assembly with a high flux of thermal and resonance neutrons

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12051

2020

Link zum Volltext

Verfügbarkeit prüfen

Scientific and technical problems of CNFC in two-component NPE and their solution in "Proryv" project

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12001

2020

Link zum Volltext

Verfügbarkeit prüfen

Development of the general design of the industrial energy complex with CNFC

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12007

2020

Link zum Volltext

Verfügbarkeit prüfen

Optimization of Two-Component Nuclear Power System

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12003

Muraviev, E V

2020

Link zum Volltext

Verfügbarkeit prüfen

1 – 25 von 560

Suche als RSS-Feed

Aktive Filter

ThemaChemical Engineering

ThemaEnergy & Fuels

Zeitschrift / SerieJournal Of Physics. Conference Series

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(560)
Mit Volltextzugriff
(560)

Publikationsform

Artikel
(560)

Sprache

Englisch
(560)
Japanisch
(2)

Erscheinungsjahr

n.n

Thema

15 weitere anzeigen...

Weniger anzeigen...

Kollektion

EZB Electronic Journals Library
(560)

Neu hinzugefügt

... seit 90 Tagen
(5)

Menü

Weitere Dienste

Einstellungen

Equilibrium Core Design of Reaktor Daya Eksperimental

Safety assessment of pressure vessel components for Reaktor Daya Eksperimental

Semi-Analytical Methods and Simulation for Temperature Distribution of Helium Purification System for Reaktor Daya Eksperimental

R&D on Surrogate Kernel Fabrication in Support of Reaktor Daya Eksperimental (RDE) Project

Preliminary Development of the FPGA based Reactor Protection Systems for Reaktor Daya Eksperimental (RDE)

Considerations of Material Selection for Control Rod Drive Mechanism of Reaktor Daya Eksperimental

Sensitivity of heat transfer parameters on the Reaktor Daya Eksperimental - RDE core

Investigation of graphite matrix activation in the fuel pebble of Reaktor Daya Eskperimental

Study of structure systems and components classification of Reaktor Daya Eksperimental - RDE based on life cycle management

Modeling of BN-600 Hybrid Core Benchmark (HEX-Z) with MCU-PTR and SERPENT 2

To estimate reliability of hydroaccumulator system of nuclear power plants and improve its design and reliability

Physical aspects for involvement of thermonuclear reactors into nuclear power systems

Possibilities and Features of REMIX Technology as an Initial Stage in the Establishing of a Full-Scale Two-Component Nuclear Energy System

Preliminary Development of Online Remote Multipurpose Reactor Monitoring System

The main problems of transmutation of actinides and long-lived fission products from NPP spent fuel

Possible ways to solve the problems of using MOX fuel in thermal reactors

Investigation of radiation levels in the region of fuel-transfer cask for transportation of spent fuel of light-water reactors

Analysis of the connection of an idle MCP with three operating without a preliminary reduction in the power of the VVER-1000 reactor

Role of fast sodium reactors in closure of the nuclear fuel cycle in the nuclear power system

Program for CNFC R&D using BN-800

Modeling the core of a lead-cooled reactor

Research study of possibility producing radioisotope Mo-99 in the active core of the BN-600 reactor using an irradiated assembly with a high flux of thermal and resonance neutrons

Scientific and technical problems of CNFC in two-component NPE and their solution in "Proryv" project

Development of the general design of the industrial energy complex with CNFC

Optimization of Two-Component Nuclear Power System

Aktive Filter

Suchergebnisse filtern