다중혈관 관상동맥 환자에서 y-문합을 이용하여 양쪽 내흉동맥만을 사용한 우회술의 조기 성적

OUTPU T 29 OUTPU T 30 OUTPU T 31 OUTPU T 32 OUTPU T 25 OUTPU T 26 OUTPU T 27 OUTPU T 28 OUTPU T 21 OUTPU T 22 OUTPU T 23 OUTPU T 24 OUTPU T 17 OUTPU T 18 OUTPU T 19 OUTPU T 20 OUTPU T 13 OUTPU T 14 OUTPU T 15 OUTPU T 16 OUTPU T 9 OUTPU T 10 OUTPU T 11 OUTPU T 12 OUTPU T 5 OUTPU T 6 OUTPU T 7 OUTPU T 8 OUTPU T 1 OUTPU T 2 OUTPU T 3 OUTPU T 4 29 30 31 32 25 26 27 28 21 22 23 24 17 18 19 20 13 14 15 16 9

A User’s Guide

Modern Nuclear Data Evaluation with the TALYS Code System

http://oa.upm.es/35412/7/INVE_MEM_2013_192429.pdf

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

TENDL: complete nuclear data library for innovative nuclear science and technology

W and W-alloys are among the primary candidate materials for plasma-facing components in the design of fusion reactors, particularly in high-heat-flux regions such as the divertor. Under neutron irradiation W undergoes transmutation to its near-neighbours in the periodic table. Additionally He and H are particles emitted from certain neutron-induced reactions, and this is particularly significant in fusion research since the presence of helium in a material can cause both swelling and a strong increase in brittleness. This paper presents the results of inventory burn-up calculations on pure W and gives quantitative estimates for He production rates in both a fusion-reactor environment and under conditions expected in the ITER experimental device. Transmutation reactions in possible alloying elements (Re, Ta, Ti and V), which could be used to reduce the brittleness of pure W, are also considered. Additionally, for comparison, the transmutation of other fusion-relevant materials, including Fe and SiC, are presented.

https://iopscience.iop.org/article/10.1088/0029-5515/51/4/043005/pdf

Neutron-induced transmutation effects in W and W-alloys in a fusion environment

The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a significant life-limiting impact on reactor components in both experimental and commercial fusion devices. As well as producing defects, the neutrons bombarding the materials initiate nuclear reactions, leading to transmutation of the elemental atoms. Products of many of these reactions are gases, particularly helium, which can cause swelling and embrittlement of materials.This paper integrates several different computational techniques to produce a comprehensive picture of the response of materials to neutron irradiation, enabling the assessment of structural integrity of components in a fusion power plant. Neutron-transport calculations for a model of the next-step fusion device DEMO reveal the variation in exposure conditions in different components of the vessel, while inventory calculations quantify the associated implications for transmutation and gas production. The helium production rates are then used, in conjunction with a simple model for He-induced grain-boundary embrittlement based on electronic-structure density functional theory calculations, to estimate the timescales for susceptibility to grain-boundary failure in different fusion-relevant materials. There is wide variation in the predicted grain-boundary-failure lifetimes as a function of both microstructure and chemical composition, with some conservative predictions indicating much less than the required lifetime for components in a fusion power plant.

https://www.iter.org/doc/www/content/com/Lists/Stories/Attachments/1384/NUCFUS.pdf

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation

Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials

In the European fusion programme, safety and environmental issues are of great importance in the continuing development of power plants. In support of this programme, a sound, complete and reliable neutron-induced cross section data library is required. The European Activation File (EAF) project has been an ongoing process performed through European and world-wide co-operation that has led to the creation of succeeding EAF versions. The latest release, EAF-2005, in a significant change from previous versions has an upper energy limit of 60 rather than 20 MeV. EAF2005 has benefited from the generation and maintenance of comprehensive activation files and the development of the processing code SAFEPAQ-II. Cross section validation exercises against both experimental data and systematics, which were started on the EAF-4 file, enable a comprehensive assessment of the data. SAFEPAQII is used to apply a series of modifications to the original source data. A very important set of modifications concerns renormalisation and branching using experimental or systematic data. A total of 7,268 reactions have been so changed; 12% of all the reactions. These are challenging tasks when the source contains nonthreshold reactions with an energy dependent branching ratio. Although EAF-2005 is the best-validated cross section library in the world, currently less than 3% of all the reactions can be compared with experimental information, and sometimes then only for very limited, and not always fusion relevant, energy ranges. As with EAF-2001 and -2003, results of integral experiments have been used to correct, adjust and validate data. This can be done using SAFEPAQ-II by inputting the measured effective cross sections. Validation using integral data has been performed by means of direct comparison with measurements of various materials under fusionrelevant neutron spectra. Irradiations have been carried out at ENEA FNG, FZK Isochron-cyclotron, Sergiev Posad SNEG-13, TUD, Ře and JAERI FNS and integral C/E comparisons made (C/E is the ratio of the library to the experimental value). The results of these benchmarking exercises have indicated, in conjunction with differential data, where modifications to the data can be applied. The EAF-2005 library contains 62,637 excitation functions involving 775 different targets from H to Fm, atomic numbers 1 to 100, in the energy range 10 eV to 60 MeV. The 3,472,000 lines that make up the point-wise file are then processed into numerous group-wise files with different micro-flux weighting spectra to meet various user needs. Uniquely, an uncertainty file is also provided that quantifies the degree of confidence placed on the data for each reaction channel.

J.-Ch. Sublet

Papers

TENDL: complete nuclear data library for innovative nuclear science and technology

Neutron-induced transmutation effects in W and W-alloys in a fusion environment

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation

Neutron-induced dpa, transmutations, gas production, and helium embrittlement of fusion materials

The European Activation File: EAF-2005 cross section library