• Nuclear industry
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• v.7 no.5 s.51
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• pp.88-90
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• 1987

장수명화가 자본비를 상당히 낮추는데 연결이 되면 원자력발전의 경제성 향상의 하나의 방향이 되는 것으로 주목되고 있다.

• Nuclear industry
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• v.18 no.12 s.190
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• pp.46-53
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• 1998

• Nuclear industry
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• v.35 no.8
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• pp.68-71
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• 2015

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.552.1-552
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• 2001

• Nuclear industry
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• v.25 no.4 s.266
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• pp.4-7
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• 2005

• Nuclear Engineering and Technology
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• v.49 no.6
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• pp.1226-1233
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• 2017

Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. The database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.

• Nuclear industry
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• v.7 no.7 s.53
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• pp.61-61
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• 1987

다음 세기 이후는 어느 정도 개발이 진행된 나라들의 생활개선도 병행하여 석유나 천연가스 자원의 감소가 현저히 나타날 것임을 강조, 원자력이나 석탄과 같은 양이 많고 또 값싼 자원으로 옮겨갈 것으로 보고 있다.

• Nuclear Engineering and Technology
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• v.50 no.2
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• pp.280-291
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• 2018

In the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code Benchmark Phase I was organized in 2010-2013. It consisted of four experiments on highly irradiated fuel rodlets tested under different experimental conditions. This benchmark revealed the need to better understand the basic models incorporated in each code for realistic simulation of the complicated integral RIA tests with high burnup fuel rods. A second phase of the benchmark (Phase II) was thus launched early in 2014, which has been organized in two complementary activities: (1) comparison of the results of different simulations on simplified cases in order to provide additional bases for understanding the differences in modelling of the concerned phenomena; (2) assessment of the uncertainty of the results. The present paper provides a summary and conclusions of the second activity of the Benchmark Phase II, which is based on the input uncertainty propagation methodology. The main conclusion is that uncertainties cannot fully explain the difference between the code predictions. Finally, based on the RIA benchmark Phase-I and Phase-II conclusions, some recommendations are made.

• Nuclear Engineering and Technology
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• v.46 no.3
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• pp.313-342
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• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• Nuclear industry
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• v.18 no.9 s.187
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• pp.66-77
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• 1998

온실 가스 배출로 인하여 지구 온난화 문제가 심각성을 더해가고 있는 차제에 지난해(1997) 12월 일본 교토에서 제3차 기후변화협약 조약국 회의가 개최되었으며, 회의 결과 일차적으로 선진국에서 온실 가스 배출 감축 목표를 설정하여 2008년부터 시행토록 합의하였다. 우리 나라는 이 회의에서 온실 가스 배출 감축 대상국에서는 제외되었지만 OECD에 가입한 국가로서 멀지 않아 감축 목표 이행 대상국에 들게 될 것으로 예측된다. 이와 관련하여 OECD/NEA는 지난 4월 $\ulcorner$원자력발전과 기후변화$\lrcorner$라는 보고서를 발표하였다. 이 보고서는 비교적 최근의 연구 자료를 인용하여 원자력이 온실 가스 배출 억제에 어떤 역할을 하는가를 연구한 내용으로서 우리 나라에서도 에너지 정책 입안 등에 도움이 될 것으로 판단된다.