• Nuclear Engineering and Technology
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• v.42 no.4
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• pp.339-364
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• 2010

Following a joint OECD/NEA-IAEA-sponsored meeting to define the current role and future perspectives of the application of Computational Fluid Dynamics (CFD) to nuclear reactor safety problems, three Writing Groups were created, under the auspices of the NEA working group WGAMA, to produce state-of-the-art reports on different aspects of the subject. The work of the second group, WG2, was to document the existing assessment databases for CFD simulation in the context of Nuclear Reactor Safety (NRS) analysis, to gain a measure of the degree of quality and trust in CFD as a numerical analysis tool, and to take initiatives to extend the existing databases. The group worked over the period of 2003-2007 and produced a final state-of-the-art report. The present paper summarises the material gathered during the study, illustrating the points with a few highlights. A total of 22 safety issues were identified for which the application of CFD was considered to potentially bring real benefits in terms of better understanding and increased safety. A list of the existing databases was drawn up and synthesised, both from the nuclear area and from other parallel, non-nuclear, industrial activities. The gaps in the technology base were also identified and discussed. In order to initiate new ways of bringing experimentalists and numerical analysts together, an international workshop -- CFD4NRS (the first in a series) -- was organised, a new blind benchmark activity was set up based on turbulent mixing in T-junctions, and a Wiki-type web portal was created to offer online access to the material put together by the group giving the reader the opportunity to update and extend the contents to keep the information source topical and dynamic.

• Nuclear industry
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• v.7 no.8 s.54
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• pp.18-19
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• 1987

경제협력개발기구/원자력기관(OECD/NEA)은 6월 17일 가맹국의 원자력발전과 핵연료주기에 관한 테이터를 집계, 공표하였다. 다음은 이중에서 원자력발전량과 우라늄농축 등에 관한 2000년대까지의 OECD 각국의 규모, 유급예측 등을 소개한 것이다(수치는 잠정치, 예측치 등을 포함)

• Nuclear industry
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• v.8 no.10 s.68
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• pp.72-74
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• 1988

경제협력개발기구$\cdot$원자력기관(OECD$\cdot$NEA)이 최근에 발표한 조사보고서에 의하면 OECD가맹국의 1987년도 원자력발전량은 전년도보다 $5.9\%$ 증가한 1조 3,126억kWh에 이르렀으며, OECD지역내의 원자력점유율도 전년보다 $0.4\%$ 증가한 $22.5\%$ 로서 점진적 진전을 보이고 있다.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.57-58
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.127-128
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• 2004

• Proceedings of the KIEE Conference
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• 2015.07a
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• pp.483-484
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• 2015

• Current Industrial and Technological Trends in Aerospace
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• v.7 no.1
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• pp.97-104
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• 2009

Successful separation of satellites from launch vehicles and release its appendages such as solar arrays and antennas are one of the most important tasks for mission accomplishment during in-orbit maneuver. Especially, specific release devices called NEA(Non-Explosive Actuator) have been widely adopted to perform safe separation and release due to its outstanding performance of low functional shock (below 500g), no contamination and easy handing as opposed to the pyroshock device. In the paper, various kinds of NEA and its history of development are reviewed along with a summary on the domestic research trend.

• Journal of Korean Library and Information Science Society
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• v.40 no.2
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• pp.311-333
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• 2009

The purpose of this study is to investigate the characteristics of 'The Big Read(TBR)' reading initiatives sponsored by the National Endowment for the Arts(NEA) in the U.S.A. TBR was originally launched to improve the seriously low level of literary reading among the American adults reported in several NEA reports, and spread to more than 500 communities. The major characteristics of TBR include the following: First, a massive investment of federal funds as well as various private and corporate donations; Second, the strong recognition of libraries as the core of reading activities in communities; Third, the adoption of the model of 'One Book, One Community' reading promotion campaign; Fourth, the provision of high quality resources for reading activities.

• Nuclear Engineering and Technology
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• v.52 no.7
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• pp.1355-1366
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• 2020

A review of the documentation and an interpretation of the NEA-1517/74 and NEA-1517/80 shielding benchmarks (measurements of photon leakage flux from a hollow sphere with a central 14 MeV neutron source) from the SINBAD database with the Monte Carlo code MCS and the most up-to-date ENDF/B-VIII.0 neutron data library are conducted. The two analyzed benchmarks describe satisfactorily the energy resolution of the photon detector and the geometry of the spherical samples with inner beam tube, tritium target and cooling water circuit, but lack information regarding the detector geometry and the distances of shields and collimators relatively to the neutron source and the detector. Calculations are therefore conducted for a sphere model only. A preliminary verification of MCS neutron-photon calculations against MCNP6.2 is first conducted, then the impact of modelling the inner beam tube, tritium target and cooling water circuit is assessed. Finally, a comparison of calculated results with the libraries ENDF/B-VII.1 and ENDF/B-VIII.0 against the measurements is conducted and shows reasonable agreement. The MCS and MCNP inputs used for the interpretation are available as supplementary material of this article.

• Nuclear Engineering and Technology
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• v.49 no.2
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• pp.327-334
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• 2017

Common-cause failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common Cause Data Exchange (ICDE) project was initiated by several countries in 1994. Since 1997 it has been operated within the Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) framework and has successfully been operated over six consecutive terms (the current term being 2015-2017). The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modeling. As CCF events are typically rare, most countries do not experience enough CCF events to perform meaningful analyses. Data combined from several countries, however, have yielded sufficient data for more rigorous analyses. The ICDE project has meanwhile published 11 reports on the collection and analysis of CCF events of specific component types (centrifugal pumps, emergency diesel generators, motor operated valves, safety and relief valves, check valves, circuit breakers, level measurement, control rod drive assemblies, and heat exchangers) and two topical reports. This paper presents recent activities and lessons learnt from the data collection and the results of topical analysis on emergency diesel generator CCF impacting entire exposed population.