http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
- 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
- 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
RISS 인기검색어
- 검색키워드
- 저자 : Ogando (검색결과 2 건)
- 무료
- 기관 내 무료
- 유료
-
P. Sauvan,A. Mayoral,J. Sanz,F. Ogando,M. Garcia,D. Lopez 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Some of the current accelerator programs such as TechnoFusion, Spiral2 or EVEDA/IFMIF will use low energy particles such as proton, deuteron and alpha. For these projects, the radioprotection studies require a more reliable prediction of the neutron and photon generated by interaction of these charged particles. In this paper, some developments to address this issue are presented. Except for proton, Monte Carlo codes such MCNPX or PHITS use built-in semi-empirical nuclear models to deal with charged particles interactions. Such models, applied to the above mentioned accelerators beam characteristics (particle type and energy), lead to unreliable prediction of secondary particle production. Consequently, there is a need to both generate accurate evaluated data libraries for light ion nuclear reactions and extend MCNPX to handle the evaluated charged particle nuclear data. The MCNPX code has been extended by the authors to handle proton, deuteron, triton and alpha nuclear data libraries. This tool is here presented and applied to analyse the reliability of available evaluated nuclear data for incident deuterons of energies those used in the abovementioned facilities (up to 40 MeV). Deuteron-induced reactions have been chosen because this particle is expected to be used in all these facilities. Concerning target material, copper has been selected as it is one the main constituents of accelerating components and beam dumps. The evaluated nuclear data are provided by the TENDL library, which is the only one available for deuterons with a wide range of target elements, including those of concern for the accelerators here considered. The testing of the TENDL nuclear data is carried out by comparing existing experimental data on thick target neutron yields for the given materials with those computed by the modified MCNPX code using TENDL cross sections. As a result, the assessment of its applicability to radioprotection studies of those accelerators is discussed.
-
Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
O. Cabellos,N. Garcia-Herranz,Carlos J. Diez de la Obra,R. Alvarez-Cascos,J. Sanz,F. Ogando,P. Sauvan 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The assessment of the accuracy of parameters related to the reactor core performance (e.g. keff) and fuel cycle (e.g. isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) can be used to address by computational simulation the systematic propagation of uncertainties on the final parameters. To perform this uncertainty assessment, the ENDF covariance files (variance/correlation in energy and cross-reactions-isotopes correlations) are required.In this paper, we assess the impact of ND uncertainties on the isotopic prediction for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) for a discharge burnup of 150 GWd/tHM. The complete set of uncertainty data for cross sections (EAF2007/UN, SCALE6.0/COVA-44G), radioactive decay and fission yield data (JEFF-3.1.1) are processed and used in ACAB code.
연관 검색어 추천
이 검색어로 많이 본 자료
활용도 높은 자료
