• 제목/요약/키워드: CEFR

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병렬 말뭉치를 이용한 CEFR 기반 문장 작문 평가 (CEFR-based Sentence Writing Assessment using Bilingual Corpus)

  • 최승권;권오욱
    • 한국정보처리학회:학술대회논문집
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    • 한국정보처리학회 2023년도 추계학술발표대회
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    • pp.54-57
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    • 2023
  • CEFR(Common European Framework of Reference for Language)는 유럽 전역의 교육기관에서 언어구사 능력을 평가하는 평가 기준이다. 본 논문은 학습자가 문장 작문한 것을 CEFR 에 기반하여 평가하는 모델을 기술하는 것을 목표로 한다. CEFR 기반 문장 작문 평가는 크게 전처리 단계, 작문 단계, 평가 단계로 구성된다. CEFR 기반 문장 작문 평가 모델의 평가는 CEFR 수준별로 분류한 문장들이 전문가의 수동 분류와 일치하는 지의 정확도와 학습자가 작문한 결과의 자동 평가로 측정되었다. 실험은 독일어를 대상으로 하였으며 독일어 전공 41 명의 대학생에게 CEFR 6 등급별로 5 문장씩 총 30 문장의 2 세트를 만들어 실험을 실시하였다. 그 결과 CEFR 등급별 자동 분류는 전문가의 수동 분류와 61.67%로 일치하는 정확도를 보였다.

Predicting CEFR Levels in L2 Oral Speech, Based on Lexical and Syntactic Complexity

  • Hu, Xiaolin
    • 아시아태평양코퍼스연구
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    • 제2권1호
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    • pp.35-45
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    • 2021
  • With the wide spread of the Common European Framework of Reference (CEFR) scales, many studies attempt to apply them in routine teaching and rater training, while more evidence regarding criterial features at different CEFR levels are still urgently needed. The current study aims to explore complexity features that distinguish and predict CEFR proficiency levels in oral performance. Using a quantitative/corpus-based approach, this research analyzed lexical and syntactic complexity features over 80 transcriptions (includes A1, A2, B1 CEFR levels, and native speakers), based on an interview test, Standard Speaking Test (SST). ANOVA and correlation analysis were conducted to exclude insignificant complexity indices before the discriminant analysis. In the result, distinctive differences in complexity between CEFR speaking levels were observed, and with a combination of six major complexity features as predictors, 78.8% of the oral transcriptions were classified into the appropriate CEFR proficiency levels. It further confirms the possibility of predicting CEFR level of L2 learners based on their objective linguistic features. This study can be helpful as an empirical reference in language pedagogy, especially for L2 learners' self-assessment and teachers' prediction of students' proficiency levels. Also, it offers implications for the validation of the rating criteria, and improvement of rating system.

Europass and the CEFR: Implications for Language Teaching in Korea

  • Finch, Andrew Edward
    • 영어어문교육
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    • 제15권2호
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    • pp.71-92
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    • 2009
  • Europass was established in 2005 by the European Parliament and the Council of Europe as a single framework for language qualifications and competences, helping citizens to gain accreditation throughout the European Community. In addition, the 1996 Common European Framework of Reference for Languages: Learning, Teaching, Assessment (CEFR) provides a common basis for language syllabi, curriculum guidelines, examination, and textbooks in Europe. This framework describes the required knowledge and skills, the cultural context, and the levels of proficiency that learners should achieve. In combination, Europass and the CEFR provide employers and educational institutes with internationally recognized standards. This paper proposes that current trends such as globalization and international mobility require a similar approach to accreditation in Asia. As jobs and workers become independent of national boundaries and restrictions, it becomes necessary to educate students as multilingual world citizens, using standards that are accepted around the world. It is suggested, therefore, that assessment models such as Europass and the CEFR, along with successful language teaching models in Europe and Canada, present opportunities of adaptation for the Korean education system. Finally, rigorous teacher training to internationally recognized levels is recommended, if Korea is to produce a workforce of highly-skilled, plurilingual world citizens.

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The Ratios of CEFR-J Vocabulary Usage Compared with GSL and AWL in Elementary EFL Classrooms and Suggestions of Vocabulary Items to be Taught

  • Ohashi, Yukiko;Katagiri, Noriaki
    • 아시아태평양코퍼스연구
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    • 제1권1호
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    • pp.61-94
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    • 2020
  • The present study examined vocabulary usage in elementary English classrooms in Japan using elementary school corpus. The authors used three wordlists to benchmark the lexical items for four classes in the corpus: the CEFR-J, the General Service List (GSL), and Academic Word List (AWL). The percentage of vocabulary usage belonging to the Level A1 in the CEFR-J was below 15% (Class A: 12.1%, Class B: 12.6%, Class C: 8.9%, and Class D: 13.6%) with no statistical difference between levels. The mean ratio of Level A2 vocabulary items was below 10%, and all classes showed less than 1% of vocabulary usage for the Levels B1 and B2. Over 70% of all vocabulary items in the corpus belonged to the most frequent 1,000-word band (level 1) of the GSL, while the next most frequent word band (level 2 of the GSL and AWL) accounted for less than 10%. The results suggest that elementary school English teachers should use more vocabulary items in the CEFR-J Level A1. The findings demonstrate that elementary school teachers are less likely to expose their pupils to grammatically well-structured sentences with an abundance of lexical items since the teachers repeatedly use the same lexemes in each class.

FAST REACTOR TECHNOLOGY R&D ACTIVITIES IN CHINA

  • Mi, Xu
    • Nuclear Engineering and Technology
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    • 제39권3호
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    • pp.187-192
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    • 2007
  • The basic research on fast reactor technology was started in the mid-1960's in China. The emphasis was put on fast reactor neutronics, thermohydraulics, sodium technology, materials, fuels, safety, sodium devices and instrumentation. In 1987, the research turned to applied basic research with the conceptual design of a 60 MW experimental fast reactor as a target. The Project of the China Experimental Fast Reactor(CEFR) with a thermal power 65 MW was launched in 1993. The R&D of fast reactor technology then carried out to serve a design demonstration connected with the different phases of the conceptual, preliminary and detailed design of the CEFR. Recently, three directions of fast rector technology R&D activities have been considered, and some research programs have been developed. They are: (1) R&D related to the CEFR, i.e. experiments to be conducted on the CEFR for its safe operation, (2) R&D related to the projects of a prototype and the demonstration of fast reactors, and(3) advanced SFR technology within the framework of the international cooperation of INPRO and GIF.

Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F

  • Tran, Tuan Quoc;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • 제54권7호
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    • pp.2635-2649
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    • 2022
  • CEFR is a small core-size sodium-cooled fast reactor (SFR) using high enrichment fuel with stainless-steel reflectors, which brings a significant challenge to the deterministic methodologies due to the strong spectral effect. The neutronic simulation of the start-up experiments conducted at the CEFR have been performed with a deterministic code system RAST-F, which is based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo (MC) code and a multi-group nodal diffusion solver. The RAST-F results were compared against the measurement data. Moreover, the characteristic of neutron spectrum in the fuel rings, and adjacent reflectors was evaluated using different models for generation of accurate nuclear libraries. The numerical solution of RAST-F system was verified against the full core MC solution MCS at all control rods fully inserted and withdrawn states. A good agreement between RAST-F and MCS solutions was observed with less than 120 pcm discrepancies and 1.2% root-mean-square error in terms of keff and power distribution, respectively. Meanwhile, the RAST-F result agreed well with the experimental values within two-sigma of experimental uncertainty. The good agreement of these results indicating that RAST-F can be used to neutronic steady-state simulations for small core-size SFR, which was challenged to deterministic code system.

Vocabulary Analyzer Based on CEFR-J Wordlist for Self-Reflection (VACSR) Version 2

  • Yukiko Ohashi;Noriaki Katagiri;Takao Oshikiri
    • 아시아태평양코퍼스연구
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    • 제4권2호
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    • pp.75-87
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    • 2023
  • This paper presents a revised version of the vocabulary analyzer for self-reflection (VACSR), called VACSR v.2.0. The initial version of the VACSR automatically analyzes the occurrences and the level of vocabulary items in the transcribed texts, indicating the frequency, the unused vocabulary items, and those not belonging to either scale. However, it overlooked words with multiple parts of speech due to their identical headword representations. It also needed to provide more explanatory result tables from different corpora. VACSR v.2.0 overcomes the limitations of its predecessor. First, unlike VACSR v.1, VACSR v.2.0 distinguishes words that are different parts of speech by syntactic parsing using Stanza, an open-source Python library. It enables the categorization of the same lexical items with multiple parts of speech. Second, VACSR v.2.0 overcomes the limited clarity of VACSR v.1 by providing precise result output tables. The updated software compares the occurrence of vocabulary items included in classroom corpora for each level of the Common European Framework of Reference-Japan (CEFR-J) wordlist. A pilot study utilizing VACSR v.2.0 showed that, after converting two English classes taught by a preservice English teacher into corpora, the headwords used mostly corresponded to CEFR-J level A1. In practice, VACSR v.2.0 will promote users' reflection on their vocabulary usage and can be applied to teacher training.

Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests

  • Guo, Hui;Jin, Xin;Huo, Xingkai;Gu, Hanyang;Wu, Haicheng
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3888-3896
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    • 2022
  • Nuclear data is the basis of reactor physics analysis. This paper aim at studying the influence of major evaluated nuclear data libraries, CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, and JENDL-4.0u, on the neutronics modelling of CEFR start-up tests. Results show these four libraries have a good performance and consistency in the modelling CEFR start-up tests. The JEFF-3.3 results exhibit only an 8 pcm keff difference with the measurement. The difference in criticality is decomposed by nuclide, which shows the large overestimation of CENDL-3.2 is mainly from the cross-section of 52Cr. Except for few cases, the calculation results are within 1σ of measurement uncertainty in control rod worth, sodium void reactivity, temperature reactivity, and subassembly swap reactivity. In the evaluation of axial and radial reaction distribution, there are about 65% of relative errors that are less than 5% and 82% of relative errors that are less than 10%.

Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

  • Guo, Hui;Huo, Xingkai;Feng, Kuaiyuan;Gu, Hanyang
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3897-3908
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    • 2022
  • High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project on "Neutronics Benchmark of CEFR Start-Up Tests" offers valuable data for the qualification of nuclear data libraries and neutronics codes. This paper focuses on the verification and validation of the CEFR start-up modelling using OpenMC Monte-Carlo code against the experimental measurements. The OpenMC simulation results agree well with the measurements in criticality, control rod worth, sodium void reactivity, temperature reactivity, subassembly swap reactivity, and reaction distribution. In feedback coefficient evaluations, an additional state method shows high consistency with lower uncertainty. Among 122 relative errors in the benchmark of the distribution of nuclear reaction, 104 errors are less than 10% and 84 errors are less than 5%. The results demonstrate the high reliability of OpenMC for its application in fast reactor simulations. In the companion paper, the influence of cross-section libraries is investigated using neutronics modelling in this paper.

CEFR control rod drop transient simulation using RAST-F code system

  • Tuan Quoc Tran;Xingkai Huo;Emil Fridman;Deokjung Lee
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4491-4503
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    • 2023
  • This study aimed to verify and validate the transient simulation capability of the hybrid code system RAST-F for fast reactor analysis. For this purpose, control rod (CR) drop experiments involving eight separate CRs and six CR groups in the China Experimental Fast Reactor (CEFR) start-up tests were utilized to simulate the CR drop transient. The RAST-F numerical solution, including the neutron population, time-dependent reactivity, and CR worth, was compared against the measurement values obtained from two out-of-core detectors. Moreover, the time-dependent reactivity and CR worth from RAST-F were verified against the results obtained by the Monte Carlo code Serpent using continuous energy nuclear data. A code-to-code comparison between Serpent and RAST-F showed good agreement in terms of time-dependent reactivity and CR worth. The discrepancy was less than 160 pcm for reactivity and less than 110 pcm for CR worth. RAST-F solution was almost identical to the measurement data in terms of neutron population and reactivity. All the calculated CR worth results agreed with experimental results within two standard deviations of experimental uncertainty for all CRs and CR groups. This work demonstrates that the RAST-F code system can be a potential tool for analyzing time-dependent phenomena in fast reactors.