Digitale Landesbibliothek Berlin Logo

Dynamic characteristics tests of full-scale lead rubber bearing (LRB) / Mori, Kentaro (Rights reserved)

Access restriction

Eingeschränkter Zugang mit Nutzungsbeschränkungen: Das Dokument ist in den Räumen der Zentral- und Landesbibliothek mit dem "Virtuellen Lesesaal der Landesbibliothek" auf allen Internet-Arbeitsplätzen zugreifbar, darf jedoch nicht kopiert, versendet oder in einem Umfang von mehr als 10% ausgedruckt werden. Weitere Informationen.

Copyright

No licence for use has been granted - all rights reserved.

Bibliographic data

Contents : Dynamic characteristics tests of full-scale lead rubber bearing (LRB) / Mori, Kentaro (Rights reserved)

Access restriction

Eingeschränkter Zugang mit Nutzungsbeschränkungen: Das Dokument ist in den Räumen der Zentral- und Landesbibliothek mit dem "Virtuellen Lesesaal der Landesbibliothek" auf allen Internet-Arbeitsplätzen zugreifbar, darf jedoch nicht kopiert, versendet oder in einem Umfang von mehr als 10% ausgedruckt werden. Weitere Informationen.

Copyright

No licence for use has been granted - all rights reserved.

Files

Restricted access: The document can be accessed only at the computer workstations of the Zentral- and Landesbibliothek Berlin. Here you can find our current opening hours.

Unlock

Dynamic characteristics tests of full-scale lead rubber bearing (LRB) / Mori, Kentaro (Rights reserved)

You can request access to this file here. You will receive an e-mail confirming that we have successfully received your request.

Dynamic characteristics tests of full-scale lead rubber bearing (LRB) / Mori, Kentaro (Rights reserved)

The access to this file is restricted.

Which word does not fit into the series: car green bus train:

I hereby confirm the use of my personal data within the context of the enquiry made.

Monograph

Author:
Kiessling, Alexius
Title:
Kiessling's Berliner Baedeker : praktischer Führer durch Berlin und Potsdam nebst Umgebungen / Alexius Kiessling
Edition:
Fünfzehnte Auflage, durchweg neu bearbeitet
Publication:
Berlin: Verlag von Alexius Kiessling, 1890/91
Language:
German
Digitization:
Berlin: Zentral- und Landesbibliothek Berlin, 2020
Scope:
128 Seiten
Note:
In der Digitalisierungsvorlage nicht enthalten: X. Neuester Plan der Stadt Berlin in Farbendruck
Keywords:
Berlin ; Potsdam ; Führer
Berlin:
B 22 Berlinführer bis 1945
DDC Group:
914.3 Landeskunde Deutschlands
URN:
urn:nbn:de:kobv:109-1-15415457
Collection:
General Regional Studies
Location:
Zentral- und Landesbibliothek Berlin
Shelfmark:
B 22/43:15.1890/91
Copyright:
Public Domain
Accessibility:
Free Access
Author:
Kiessling, Alexius
Title:
Kiessling's Berliner Baedeker : praktischer Führer durch Berlin und Potsdam nebst Umgebungen / Alexius Kiessling
Edition:
Fünfzehnte Auflage, durchweg neu bearbeitet
Publication:
Berlin: Verlag von Alexius Kiessling, 1890/91
Language:
German
Digitization:
Berlin: Zentral- und Landesbibliothek Berlin, 2020
Scope:
128 Seiten
Note:
In der Digitalisierungsvorlage nicht enthalten: X. Neuester Plan der Stadt Berlin in Farbendruck
Keywords:
Berlin ; Potsdam ; Führer
Berlin:
B 22 Berlinführer bis 1945
DDC Group:
914.3 Landeskunde Deutschlands
URN:
urn:nbn:de:kobv:109-1-15415457
Collection:
General Regional Studies
Location:
Zentral- und Landesbibliothek Berlin
Shelfmark:
B 22/43:15.1890/91
Copyright:
Public Domain
Accessibility:
Free Access

Contents

Table of contents

  • Kerntechnik (Rights reserved)
  • Calendar of Events (CC BY)
  • Economic and financial approaches to spent nuclear fuel, radioactive waste, and decommissioning: an international review and implications for Türkiye / Kilic, Semih Sadi (CC BY)
  • Kinematic analysis of a novel 2P4R 6DoF manipulator of 9DoF heavy duty arm having less average error than 6R 6DoF / Raza, Muhammad Aun (CC BY)
  • Preliminary study neutronic design and optimization of a long-life gas-cooled fast reactor with modified CANDLE scheme using OpenMC / Angelina, Tsania Eksa (CC BY)
  • Preliminary neutronics design and analysis of CANDLE reactor core with UMo fuel and lead coolant / Zou, Xiaoliang (CC BY)
  • Integrated thermal-hydraulic analysis using GOTHIC code during SBO for maanshan plant / Huang, Li-Ying (CC BY)
  • Study on the influence of Ag nanofluid concentration on the performance of downward-facing heat transfer surfaces / Lin, Chenrui (CC BY)
  • Severe accident simulation of Kuosheng NPP in reactor shutdown mode with MAAP5 / Huang, Tzu-En (CC BY)
  • Forced convective condensation inside a vertical tube with a steam-noncondensable gas mixture / Maheshwari, Naresh K. (CC BY)
  • Comparative analysis of Geant4 and MACCS for nuclear accident assessment in Saudi Arabia / Baashen, Lamya (CC BY)
  • Refractive index fitting method and measurement device for particle image velocimetry applications in nuclear fuel bundle experiments / Kacz, Dániel (CC BY)
  • Assessment of radiological consequences from a hypothetical nuclear reactor accident at a proposed site in Sierra Leone / Hanciles, Milford (CC BY)
  • ˜Theœ failure probability calculation of the passive system EPS in HPR1000 under LBLOCA based on the importance sampling algorithm / Xiao, Lingmei (CC BY)
  • Atmospheric dispersion and dose assessment of key radionuclides from a hypothetical VVER-1000 accident / Kangarlou, Kambiz (CC BY)
  • Frontmatter (Rights reserved)
  • Calendar of events / Kruessenberg, Anne (CC BY)
  • EducTUM – an interactive platform for education and training in the non-destructive analysis of radioactive waste / Narr, Thomas (CC BY)
  • Participatory development and mixed-methods evaluation of immersive VR training for radiation protection and nuclear safeguards – KISS / Kettler, John (CC BY)
  • Visualization of trouble spots for decontamination work and decision measurements with the help of BIM / Müßle, Melanie (CC BY)
  • Development of a Compton camera supporting the decommissioning of nuclear facilities with advanced radiological measurements / Petrak, Sibylle (CC BY)
  • Development of a sampling system including quality assured sampling procedure for nonaccessible area (Bero) / Gack, Felix (CC BY)
  • Automated non-destructive internal corrosion detection on radioactive drums (ZIKA) / Hatz, Nick (CC BY)
  • Improved deconstruction of components in nuclear power plants through deterministic grain arrangement in diamond wire grinding / Denkena, Berend (CC BY)
  • New method of disc electrode wear monitoring in contact arc metal grinding using deep learning and signal clustering techniques / Zinkoohi, Majid (CC BY)
  • Signal-based detection of arc phenomena in underwater electrothermal cutting with CAMG for the decommissioning of nuclear facilities / Mills, Christian (CC BY)
  • Advances in nuclear decommissioning and dismantling: technologies and expertise within the FORKA research program / Spornhauer, Kerstin (CC BY)
  • ROBBE–autonomous robot-aided coating removal and decontamination of assemblies in nuclear dismantling: development and operational evaluation / Santos, Pedro (CC BY)
  • Frontmatter (Rights reserved)
  • Calendar of events (CC BY)
  • One new fuel breeding configuration for long cycle life fast spectrum reactors / Huang, Jin Feng (CC BY)
  • Comparative neutronic and radiotoxicity analysis of advanced nuclear fuels in a KLT-40S assembly / Hasan, Md Rahat (CC BY)
  • Cascade active disturbance rejection control based on IDE algorithm for once-through steam generator pressure / Guo, Wei (CC BY)
  • Safety analysis of small modular natural circulation lead-cooled fast reactors SNCLFR-100 during unprotected loss of heat sink and protected loss of heat sink transients / Yan, Yulin (CC BY)
  • Passive safety systems and heat pipe applications in nuclear power plants / Elbaz, Mohamed Ahmed (CC BY)
  • Multi-channel GOTHIC model of a postulated spent fuel pool leakage accident for the Maanshan PWR units / Chen, Yen-Shu (CC BY)
  • Frontmatter (Rights reserved)
  • Calendar of events (Rights reserved)
  • Methodology of core integrity and radiation dose assessment for postulated LOCA scenario during long-term shutdown period in Kuosheng NPP / Lee, Shiau-Yu (Rights reserved)
  • CFD analysis of various configurations of spray nozzle for ECCS system in pool type research reactor / Malik, Huzaifa (Rights reserved)
  • Gamma and neutron dose assessment for the spent fuel storage pool of a VVER-1000 reactor using an updated cross-section library under steady-state conditions / Arabzadeh, Saeedeh (Rights reserved)
  • Neutronic analysis of thorium-uranium mixed fuel for multi-application small light water reactor (MASLWR) / Ateya, Afaf A. E. (Rights reserved)
  • Research on evaluation method of NPPs operator’s response plan reliability based on Bayesian network / Yao, Kai (Rights reserved)
  • ˜Theœ measurement of the thermal neutron absorption cross sections of graphite and carbon by W. Bothe and P. Jensen – a recalculation of the experiments and the graphite problem during the early uranium work / Brockmann, Hans (Rights reserved)
  • A critique of Canadian regulatory documents for tritium emissions from NPPs / Greening, Frank R. (Rights reserved)
  • Frontmatter (Rights reserved)
  • Calendar of events (Rights reserved)
  • Safety, and security monitoring system for spent nuclear fuel dry cask storage / Wadoud, Amir A. (Rights reserved)
  • Looking for situation awareness in nuclear power plant: uncovering information requirement and influencing factors through a goal-directed task analysis / Yao, Kai (Rights reserved)
  • ˜Theœ effects of Gd and Er as burnable absorbers in VVER-1200 assembly using OpenMC: a comparative neutronic study / Tahia, Mosharat Belal (Rights reserved)
  • Constant heat flux and flow characteristics of nanofluids in an annular helical tube heat exchanger / Elkhatib, Hesham (Rights reserved)
  • Water hammer analysis of essential service water system in nuclear power plant / Yan, Sheng (Rights reserved)
  • Frontmatter (Rights reserved)
  • Calendar of events (Rights reserved)
  • Adsorption behavior of Se (Ⅳ) and Se (Ⅵ) on sodium bentonite / Huang, Cong (Rights reserved)
  • Decoupling and controller design of multivariable systems for small modular reactors / Liu, Wenqian (Rights reserved)
  • Prediction of LOCA break sizes using LSTM architecture for pressurized water reactors / Badr, Youssef (Rights reserved)
  • Numerical investigation of three-tube intertwined HX design / Khan, Muhammad Ali (Rights reserved)
  • Reliability assessment of equal height difference passive containment cooling system based on the adaptive metamodel-based subset importance sampling method in inverse uncertainty quantification framework / Jiang, Hong (Rights reserved)
  • Analysis of neutronic performance of VVER 1200 reactor using accident tolerant fuel / Aziz, Moustafa (Rights reserved)
  • Augmentation of the neutronic safety aspect of high-density fuel research reactor using new control element design / Porhemmat, Mohammad Hadi (Rights reserved)
  • Safety behaviour of a material testing reactor using U 3 Si 2 fuel during reactivity insertion accident / Selim, Hala K.G. (Rights reserved)
  • Serpent 2 simulations of the historic Haigerloch B8 nuclear reactor of 1945 / Wiesenmüller, Jan (CC BY)
  • Frontmatter (Rights reserved)
  • Thermal integrity assessment of the limiter for Pakistan Spherical Tokamak (PST) / Hussain, Ali (Rights reserved)
  • Frontmatter (Rights reserved)
  • Optimization and range expansion of IRIS reactor accident diagnosis model based on LSTM neural network / Bai, Tianze (Rights reserved)
  • Study on the diffusion behavior of rhenium in CTAB-modified bentonite / Guo, Jiacheng (Rights reserved)
  • ˜Theœ effect of ambient temperature variation on the spectrometric performance of NaI (Tl) scintillation detector; an experimental study / Mohammadnia, Meysam (Rights reserved)
  • Calendar of events (Rights reserved)
  • Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite / Shih, Yu-Hung (Rights reserved)
  • Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core / Salman, Ahmed E. (Rights reserved)
  • State-of-art review of beyond design basis evaluation approach of a generic nuclear power plant in the UK / Filipov, Svetlin (Rights reserved)
  • Frontmatter (Rights reserved)
  • Frontmatter (Rights reserved)
  • Frontmatter (Rights reserved)
  • Risk analysis and protection in case of intrusion of nuclear facilities / Wadoud, Amir A. (Rights reserved)
  • Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade / Shi, Er-bing (Rights reserved)
  • Thermo-hydraulic characteristics of molten salt NaNO 3 –KNO 3 using numerical simulations / Kudariyawar, Jayaraj Y. (Rights reserved)
  • Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines / Bachmann, Madeleine (Rights reserved)
  • Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering / Mohsen, Mohamed Y.M. (Rights reserved)
  • A comprehensive assessment on recent advancements in spent fuel reprocessing and waste management: pioneering technologies for a sustainable nuclear future / Sakthimurugan, Veeraraghavan (Rights reserved)
  • Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE / Zhang, Zhenze (Rights reserved)
  • Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose / Yinusa, Taiwo Saheed (Rights reserved)
  • Transient analyses on overpower transients of small modular natural circulation Lead-cooled fast reactor SNCLFR-100 / Song, Tianxin (Rights reserved)
  • Development of new ISO 4917 standard series for the design of nuclear power plants against seismic events / Gersinska, Rainer (Rights reserved)
  • Dynamic characteristics tests of full-scale lead rubber bearing (LRB) / Mori, Kentaro (Rights reserved)
  • Fragility analysis of nuclear steam supply system components of a pressurized water reactor / Pellissetti, Manuel (Rights reserved)
  • Calendar of events (Rights reserved)
  • Numerical modelling of creep, agin and leakage of the prestressed reinforced concrete structure. Application to concrete containment building / Meng, Try (Rights reserved)
  • Effect of glass cooling method on thermal shock behavior of nuclear waste container / Yang, Xinyi (Rights reserved)
  • Evaluating the seismic out-of-plane capacity of unreinforced masonry walls: effects of cantilevered masses / Helm, Lukas (Rights reserved)
  • Calendar of events (Rights reserved)
  • Evaluation of various calculational models of FA containing burnable absorber rod in the VVER-1000 / Ghaseminejad, Sahar (Rights reserved)
  • Innovative materials for enhancing safety, efficiency, and sustainability in nuclear waste management / Devarajan, Yuvarajan (Rights reserved)
  • Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core / Yinusa, Taiwo Saheed (Rights reserved)
  • Optimal design of an eddy current sensor for detecting and characterizing cracks by data inversion: parametric study / Barrarat, Fatima (Rights reserved)
  • Study on the impact of containment mesh refinement and PAR installation on hydrogen distribution during severe accidents / Huang, Tzu-En (Rights reserved)
  • Double solitary waves reactor / Huang, Jin Feng (Rights reserved)
  • Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys / Simbruner, Kai (Rights reserved)
  • Structural mechanics in reactor technology (SMiRT) conference series: 50th anniversary conference / Sadegh-Azar, Hamid (Rights reserved)
  • ˜Theœ RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant / Lin, Hao-Tzu (Rights reserved)
  • 15-15Ti cladding behavior during a RIA type event in TRIGA reactor / Roman, Mihaela R. (Rights reserved)
  • Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design / Wang, Yue (Rights reserved)
  • An study on seismic soil-structure interaction (SSI) effects for a base-isolated structure on firm soil / Ghiocel, Dan M. (Rights reserved)
  • Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia / Khan, Salah Ud‐Din (Rights reserved)
  • Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident / Chiang, Yu (Rights reserved)
  • Closed form formulae for two interacting equal parallel through-wall cracks embedded in an infinite elastic medium under normal tension / Gilles, Philippe (Rights reserved)
  • Calendar of events (Rights reserved)
  • Generic flame extension model development based on machine learning for NPPs fire hazard analysis (FHA) / Sharma, Pavan K. (Rights reserved)
  • A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management / Chenniappan, Thiagarajan (Rights reserved)
  • A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials / Yang, Zi-Yi (Rights reserved)
  • Frontmatter (Rights reserved)
  • Large-scale PANDA facility – radiation experiments and CFD calculations / Kapulla, Ralf (Rights reserved)
  • Analysis of hypothetical channel flow blockage of a tubular fuel assembly in a 10 MWth nuclear research reactor / Ibrahim, Said M. A. (Rights reserved)
  • Improved intelligent model predictive controller for the nuclear power reactor system / Mostafa, Khaled M. (Rights reserved)
  • Investigating advection–dispersion behavior for simulation of HTO and 238 Pu transport in argillaceous shale with different varying degrees of weathering / Yunfeng Shi (Rights reserved)
  • Frontmatter (Rights reserved)
  • Scaling factors for CANDU reactor waste: how reliable are they? / Greening, Frank R. (Rights reserved)
  • Study on advection–dispersion behavior for simulation of 3 H, 99 Tc, and 90 Sr transport in crushed sandstone of column experiments / Shih, Yu-Hung (Rights reserved)
  • Transient thermal analysis for optimal armor material in upgraded mockup for PST using MOOSE Framework / Rahman, Habib Ur (Rights reserved)
  • Coupled AC 2 -CFD simulations for a high-pressure core melt accident scenario / Herb, Joachim (Rights reserved)
  • Analyses of the unavailability dynamics of emergency core cooling system / Farcasiu, Mita (Rights reserved)
  • Calendar of events / Kruessenberg, Anne (Rights reserved)
  • Frontmatter (Rights reserved)
  • Frontmatter (Rights reserved)
  • Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops / Gaikwad, Avinash J. (Rights reserved)
  • Implementation of the preCICE coupling interface for AC 2/ATHLET / Herb, Joachim (Rights reserved)
  • System theory safety analysis of network malfunction in nuclear power plant distributed control systems / Beini, Xiong (Rights reserved)
  • Study of reliability prediction method and uncertainty analysis of the pump and valve of a floating nuclear power plant / Yin, Changzheng (Rights reserved)
  • Overview on GRS CFD activities related to containment applications / Stewering, Jörn (Rights reserved)
  • Synthesis, structural transformation and magnetic properties of the Nd (III)-doped Fe 3− x Nd x O 4 (0 ≤ x  ≤ 0.9): an analogue for actinicles immobilization / Wang, Zaihong (Rights reserved)
  • Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code / Yu, Cheng-Lun (Rights reserved)
  • An artificial neural network-based numerical estimation of the boiling pressure drop of different refrigerants flowing in smooth and micro-fin tubes / Çolak, Andaç Batur (Rights reserved)
  • A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis / Yang, Wudi (Rights reserved)
  • ˜Theœ 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows / Papukchiev, Angel (Rights reserved)
  • ˜Theœ European GO-VIKING project on flow-induced vibrations: overview and current status / Papukchiev, Angel (Rights reserved)
  • Numerical simulation analysis of high-temperature bent sodium heat pipes / Cheng, Xiongwei (Rights reserved)
  • Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor / El-Morshedy, Salah El-Din (Rights reserved)
  • Preliminary neutronic analyses for annular VHTR with different coated fuel particle designs / Sambuu, Odmaa (Rights reserved)
  • Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor / Lotfalian, Mohammadreza (Rights reserved)
  • A detection and defense security system design for nuclear waste storage against stealth terrorists attack / Wadoud, Amir A. (Rights reserved)
  • Fuzzy reliability algorithm for the shutdown system of research reactor / Selim, Hala K. G. (Rights reserved)
  • Testing the thermal performance of water cooling towers / El-Morshedy, Salah El-Din (Rights reserved)
  • Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production / D., Christopher Selvam (Rights reserved)
  • A blockchain based scheme for distributed storage of nuclear power plant images / Goru, Kalivaraprasanna Babu (Rights reserved)
  • Monte Carlo simulation of photo-peak efficiency response function and calculation of total efficiency for a NaI (Tl) scintillator detector / Sadeghi, Nahid (Rights reserved)
  • Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers / Hosseinimotlagh, Seyede Nasrin (Rights reserved)
  • Calendar of events (Rights reserved)
  • Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant / Wang, Lingzhi (Rights reserved)
  • Calculation and application research on real-time source term diffusion in NPP auxiliary building under accident circumstances / Xie, Mingliang (Rights reserved)
  • CFD simulation on droplet behaviour in post-dryout region / Xia, Zihan (Rights reserved)
  • Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants / Wang, Fanyu (Rights reserved)
  • Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment / Yang, Zhi (Rights reserved)
  • Study on spent fuel heatup during spent fuel pool complete loss of coolant accident / Shih, Yu-Huai (Rights reserved)
  • Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies / Chenniappan, Thiagarajan (Rights reserved)
  • Comparison of thermal hydraulic performance between horizontal and vertical steam generators in nuclear power plants / El-Sahlamy, Neama M. (Rights reserved)
  • Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor / Ibrahim, Amr (Rights reserved)
  • Frontmatter (Rights reserved)
  • Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation / Shakir, Sehrish (Rights reserved)
  • Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators / Farzampanah, Farzaneh (Rights reserved)
  • CTAB modification bentonite for enhanced Re adsorption and diffusion suppression / Jiang, Qifeng (Rights reserved)
  • Reliability analysis of digital reactor protection systems in floating nuclear power plants / Xie, Xi-Wen (Rights reserved)
  • Calendar of events / Kruessenberg, Anne (Rights reserved)
  • Calendar of events / Kruessenberg, Anne (Rights reserved)
  • Calendar of events (Rights reserved)
  • CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges / Liao, Yixiang (Rights reserved)
  • Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction / Ndayiragije, Jean Pierre (Rights reserved)
  • Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE / Chiang, Yu (Rights reserved)
  • Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components / Morlova, Elena D. (Rights reserved)
  • ˜Theœ RADTRAD analysis methodology for the Fuel Handling Accident during the long-term shutdown period of Chinshan Nuclear Power Plant / Lee, Shiau-Yu (Rights reserved)
  • Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm / Ateya, Afaf A.E. (Rights reserved)
  • Frontmatter (Rights reserved)
  • Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method / Amanelahi Dorcheh, Lida (Rights reserved)
  • Methodology of probabilistic safety assessment for transportation of radioactive material / Kumar, Manorma (Rights reserved)
  • Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs) / Aziz, Moustafa (Rights reserved)
  • Comparison of modeling methods for the effective diffusivities of IO 3 − estimated in compacted bentonite using through-diffusion tests under aerobic conditions / Tsai, Tsuey-Lin (Rights reserved)
  • Thermal-hydraulic and safety analysis of alternative ceramic fuels in next generation of VVER-1000 reactor / Rahimi, Ahmad (Rights reserved)
  • Calendar of events – issue 6 of KERN / Kruessenberg, Anne (Rights reserved)
  • Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction / Gavali, Pradipkumar M. (Rights reserved)
  • Study on comprehensive evaluation method of mental workload level / Yan, Shengyuan (Rights reserved)
  • Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger / Abdul Razzaq, Ali K. (Rights reserved)
  • Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor / Yıldız, Ercan (Rights reserved)
  • A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event / Kang, Ji Su (CC BY)
  • CONTENTS/INHALT (Rights reserved)

Full text

CLASSIC
            

Downloads

Downloads

Full record

TOC
Mirador

This page

Mirador

Image fragment

Link to the viewer page with highlighted frame Link to IIIF image fragment

Formats and links

Formats and links

The metadata is available in various formats. There are also links to external systems.

Formats

METS MARC XML Dublin Core

Links

OPAC DFG-Viewer

Cite

Cite

The following citation links are available for the entire work or the page displayed:

Full record

This page

Citation recommendation

Please check the citation before using it.

Search results

Search results

11 / 43,985
Back to search results

Image manipulation tools

Tools not available

Share image region

Use the mouse to select the image area you want to share.
Please select which information should be copied to the clipboard by clicking on the link:
  • Link to the viewer page with highlighted frame
  • Link to IIIF image fragment

Contact

Have you found an error? Do you have any suggestions for making our service even better or any other questions about this page? Please write to us and we'll make sure we get back to you.

Which word does not fit into the series: car green bus train:

I hereby confirm the use of my personal data within the context of the enquiry made.