• Refine Query
  • Source
  • Publication year
  • to
  • Language
  • 100
  • 35
  • 9
  • 4
  • 4
  • 2
  • 2
  • 2
  • 1
  • 1
  • 1
  • 1
  • 1
  • 1
  • 1
  • Tagged with
  • 248
  • 248
  • 248
  • 43
  • 36
  • 30
  • 29
  • 25
  • 21
  • 20
  • 20
  • 19
  • 19
  • 18
  • 17
  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
191

Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions

Gros, Emilien B. 18 January 2012 (has links)
The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using the neutronics analysis code SCALE6.0 and the thermal-hydraulics and kinetics modeling code RELAP5-3D with objective to devise, analyze, and evaluate the feasibility and stability of a start-up procedure for this reactor using natural circulation of the coolant and under the Loss Of Offsite Power (LOOP) conditions. This Generation IV reactor design has been studied by research facilities worldwide for almost a decade. While neutronics and thermal-hydraulics analyses have been previously performed to show the performance of the reactor during normal operation and for shutdown scenarios, no study has heretofore been published to examine the active or passive start-up of the reactor. The fuel temperature (Doppler) and coolant density coefficient of reactivity of the LS-VHTR were examined using the CSAS6 module of the SCALE6.0 code. Negative Doppler and coolant density feedback coefficients were calculated. Two initial RELAP5 simulations were run to obtain the steady-state conditions of the model and to predict the changes of the thermal-hydraulic parameters during the shutdown of the reactor. Next, a series of step reactivity additions to the core were simulated to determine how much reactivity can be inserted without jeopardizing safety and the stability of the core. Finally, a start-up procedure was developed, and the restart of the reactor with natural convection of the coolant was simulated. The results of the simulations demonstrated the potential of a passive start-up of the LS-VHTR.
192

A review of the methods of economic analysis of nuclear power plants

Cavender, Brittainy Anne 01 August 2011 (has links)
Nuclear power plants across the United States are reaching the end of their current operating licenses, forcing decision makers to think about the way forward. As they consider the best alternatives for dealing with aging nuclear plants, it is becoming increasingly important to have an accurate method for calculating the long-term costs of nuclear power plants. This report begins by investigating the methodologies currently used in these calculations. They focus on the uncertainty associated with deregulated electricity markets and can be broken down into two main categories: discounted cash flow and real options analysis. Next the report discusses the limitations of the current methodologies, focusing specifically on those aspects of evaluation that are currently eclipsed by electricity market uncertainty. Finally the report offers recommendations for addressing these limitations and creating a stronger analytical framework for calculating the lifetime cost of nuclear power plants. / text
193

Anthropogenic '1'4C in the natural (aquatic) environment

Begg, Fiona H. January 1992 (has links)
No description available.
194

Desenvolvimento de sistema de monitoracao e diagnostico aplicado a valvulas moto-operadas utilizadas em centrais nucleares

CARNEIRO, ALVARO L.G. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:48:29Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:57:39Z (GMT). No. of bitstreams: 1 09059.pdf: 8640296 bytes, checksum: 8403c184612094b888b01743f050125d (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
195

Análise de defeitos em tubos de geradores de vapor de usinas nucleares utilizando a transformada de Hilbert-Huang em sinais de inspeção por correntes parasitas / Defects diagnosis of nuclear power plant steam generator tubes using the Hilbert-Huang transform in eddy current testing signals

FORMIGONI, ANDRE L. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:35:10Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:55Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
196

Cálculo de custo ambiental das usinas nucleares de Angra 1,2 e 3 utilizando o programa SIMPACTS / Calculating environmental cost of nuclear power plants Angra 1, 2 and 3 using the SIMPACTS program

MENZEL, FRANCINE 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:42:29Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:33Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
197

Modulo de extracao de eventos em assinaturas de potencia de valvulas moto-operadas, usando um sistema especialista para o sistema de diagnostico de MOV's utilizado em reatores nucleares

PERRENOUD, HELENA G. 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:46:15Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:40Z (GMT). No. of bitstreams: 1 07970.pdf: 7550264 bytes, checksum: 59898e15f47566b782c4f5d17f6a0287 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
198

Classificação de defeitos em tubos de gerador de vapor de plantas nucleares utilizando mapas auto-organizáveis

MESQUITA, ROBERTO N. de 09 October 2014 (has links)
Made available in DSpace on 2014-10-09T12:54:13Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:27Z (GMT). No. of bitstreams: 1 12432.pdf: 12974191 bytes, checksum: ddfc093df6afa20374e446cb5c994b88 (MD5) / Tese (Doutoramento) / IPEN/T / Escola Politecnica, Universidade de São Paulo - POLI/USP
199

Aplicação dos conceitos de indivíduo representativo e de grupo crítico para o controle ambiental de instalações nucleares no Brasil / The use of representative person and critical group concepts for environmental control of nuclear facilities in Brazil

FERREIRA, NELSON L.D. 10 November 2014 (has links)
Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T12:03:00Z No. of bitstreams: 0 / Made available in DSpace on 2014-11-10T12:03:00Z (GMT). No. of bitstreams: 0 / Tese (Doutorado em Tecnologia Nuclear) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
200

An investigation on the impact of procurement quality management in a nuclear power station

Gumede, Nomfusi Leticia January 2011 (has links)
Thesis (MTech (Quality))--Cape Peninsula University of Technology, 2011. / This research project in Procurement Quality Engineering was conducted at a Nuclear Power Generation Company in the Western Cape, South Africa. During the past decade, quality management has become increasingly recognised as highly desirable for all organisations at all levels. All organisations, to varied degrees, can benefit from the application of quality management skills in some parts of their daily operations. The research project will investigate the impact or effect of late deliveries of spares on the operational cost of the organisation. The organisation is not aware what impact the delivery of spares has on operating costs. Against the above background, the problem to be researched within the ambit of this dissertation reads as follows: "Poor product and / or service delivery from Vendors and / or Suppliers have an adverse impact on the output of the Procurement Quality Department" .The primary research objectives of this study are the following: ~ To emphasise the importance of quality within the supply chain. ~ To investigate the impact of non-conforming items delivered to a Nuclear Power Plant. ~ To determine measures which can be put in place to improve communication between suppliers, vendors, buyers and procurement quality engineering. ~ To determine or investigate the cost of poor quality in the organisation. ~ To improve the quality of goods and services through the application of a quality management system within the supply chain. The research method used in this research project involved both qualitative and quantitative research processes. Questionnaires and statistical techniques were used to analyse the data, and to draw conclusions and recommend possible areas for improvement. The research methodology falls within the ambit of a case study.

Page generated in 0.0558 seconds