• 제목/요약/키워드: Prompt

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DTW를 이용한 향상된 문맥 제시형 화자인식 (An Enhanced Text-Prompt Speaker Recognition Using DTW)

  • 신유식;서광석;김종교
    • 한국음향학회지
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    • 제18권1호
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    • pp.86-91
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    • 1999
  • 본 연구에서는 문맥 종속 또는 문맥 독립형 화자 인식에서의 단점을 개선하는 방법으로 문맥 제시형 화자 인식 실험을 수행하였다. 화자 인식 알고리즘으로는 개선된 Dynamic Time Warping(DTW)을 사용하였고 실시간 처리를 위하여 전체 계산량을 증가시키지 않는 아주 간단한 끝점검출알고리즘을 사용하였으며, 여러 가지 다양한 특징 파라미터를 이용하여 인식실험을 행한 결과 weighted cepstrum을 이용했을 때 가장 좋은 인식성능을 얻을 수 있었다. 실험결과 세 개의 단어를 제시하였을 경우 화자식별오류는 0.02%를 보였고, 화자확인은 문턱값을 적절히 정했을 때 사용자 거부율 1.89%, 사칭자 허용률 0.77%, 총 확인 오류0.97%를 보였다.

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다공물질 연소기의 NOx 및 CO 배출 특성 (NOx and CO Emission Characteristics of Porous Inert Medium Burner)

  • 임인권
    • 대한기계학회논문집
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    • 제19권2호
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    • pp.559-567
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    • 1995
  • The combustion process within a porous inert medium (PIM) burner is numerical studied. A detailed chemical reaction scheme including thermal and prompt NO$_{x}$ reactions is used to predict the formation and destruction of pollutants such as NO$_{x}$ and CO. The reaction paths for NO$_{x}$ formation are divided to quantify the amount of NO$_{x}$ formed through thermal NO$_{x}$ reaction or through prompt NO$_{x}$ reaction. Emission index is calculated to compare the actual mass of NO$_{x}$ or CO produced through the combustion of unit mass of fuel. It is found NO formation in PIM burner is confined in flame zone and formation is suppressed due to heat loss at down-stream of the flame. Higher production of NO through prompt NO reaction path is observed due to the higher concentration of fuel derivative species and its higher diffusion at flame front. For all equivalence ratios, CO emission within PIM burner is lower than that from the one-dimensional freely-propagating flame. PIM burner flame has better NO$_{x}$ emission index from .psi. = 0.75 to .psi. = 1.1. to .psi. = 1.1.

발단 방사화 검출기를 이용한 핵분열 즉발 중성자 에너지 스펙트럼 측정방법 (Method for Measuring Prompt Fission Neutron Energy Spectrum by Means of Threshold Activation Detectors)

  • 노성기;신희성;박종묵
    • Nuclear Engineering and Technology
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    • 제22권4호
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    • pp.410-415
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    • 1990
  • MN(Madland-Nix) 모형에 바탕을 둔 핵분열 즉발 중성자 에너지 스펙트럼을 핵분열 유기중성자의 에너지 함수로서 구했다. 이 중성자 스펙트럼을 $^{27}$ Al(n,$\alpha$), $^{32}$S(n,p) 및 $^{115}$ In(n,n') 발단 방사화 검출기의 여기함수에 증율시켜 평균핵반응 단면적을 계산하고 상호간의 비, 즉, 중성자 스펙트럼 지수를 구했다. 그 결과 핵분열 유기중성자의 에너지에 따라 중성자 스펙트럼은 변하며 그에 따라 중성자 스펙트럼 지수도 변함을 보였다. 이것은 곧 중성자 스펙트럼 지수를 실험적으로 결정하므로써 핵분열 즉발 중성자 에너지 스펙트럼을 결정할 수 있음을 의미한다.

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핵분열(核分裂) 중성자(中性子)스펙트럼이 핵임계도(核臨界度)에 미치는 효과(效果) (Effect of Prompt Fission Neutron Spectral Formulae on Nuclear Criticality)

  • 노성기;민덕기;육근억;오희필
    • Journal of Radiation Protection and Research
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    • 제7권1호
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    • pp.56-60
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    • 1982
  • 핵분열(核分裂) 즉발중성자(卽發中性子)스펙트럼의 표현식(表現式)인 왓트식(式), 크란버그식(式) 및 멕스웰식(式)을 핵분열(核分裂)의 선원항(線源項)으로 취(取)하여 고디바계(系)와 제제벨계(系)의 유효증배계수(有效增倍係數)를 ANISN 전산(電算)코드로 산출(算出)하고 타(他) 연구자(硏究者)의 실험치(實驗値)와 비교(比較)해 보았다 .그 결과(結果) 실험치(實驗値)에 가장 가까운 값을 주는 것은 멕스웰식(式)으로 보였다. 이것은 곧 멕스웰식(式)이 핵분열(核分裂) 즉발중성자(卽發中性子)스펙트럼의 적절(適切)한 표현식(表現式)임을 의미(意味)한다.

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Experimental setup for elemental analysis using prompt gamma rays at research reactor IBR-2

  • Hramco, C.;Turlybekuly, K.;Borzakov, S.B.;Gundorin, N.A.;Lychagin, E.V.;Nehaev, G.V.;Muzychka, A. Yu;Strelkov, A.V.;Teymurov, E.
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2999-3005
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    • 2022
  • The new experimental setup has been built at the 11b channel of the IBR-2 research reactor at FLNP, JINR, to study the elemental composition of samples by registration of prompt gamma emission during thermal neutron capture. The setup consists of a curved mirror neutron guide and a radiation-resistant HPGe high-purity germanium detector. The detector is surrounded by lead shielding to suppress the natural background gamma level. The sample is placed in a vacuum channel and surrounded by a LiF shield to suppress the gamma background generated by scattered neutrons. This work presents characteristics of the experimental setup. An example of hydrogen concentration determining in a diamond powder made by detonation synthesis is given and on its basis, the sensitivity of the setup is calculated being ~4 ㎍.

Upgrade of gamma electron vertex imaging system for high-performance range verification in pencil beam scanning proton therapy

  • Kim, Sung Hun;Jeong, Jong Hwi;Ku, Youngmo;Jung, Jaerin;Cho, Sungkoo;Jo, Kwanghyun;Kim, Chan Hyeong
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.1016-1023
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    • 2022
  • In proton therapy, a highly conformal proton dose can be delivered to the tumor by means of the steep distal dose penumbra at the end of the beam range. The proton beam range, however, is highly sensitive to range uncertainty, which makes accurately locating the proton range in the patient difficult. In-vivo range verification is a method to manage range uncertainty, one of the promising techniques being prompt gamma imaging (PGI). In earlier studies, we proposed gamma electron vertex imaging (GEVI), and constructed a proof-of-principle system. The system successfully demonstrated the GEVI imaging principle for therapeutic proton pencil beams without scanning, but showed some limitations under clinical conditions, particularly for pencil beam scanning proton therapy. In the present study, we upgraded the GEVI system in several aspects and tested the performance improvements such as for range-shift verification in the context of line scanning proton treatment. Specifically, the system showed better performance in obtaining accurate prompt gamma (PG) distributions in the clinical environment. Furthermore, high shift-detection sensitivity and accuracy were shown under various range-shift conditions using line scanning proton beams.

Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

  • Czakoj, Tomas;Kostal, Michal;Losa, Evzen;Matej, Zdenek;Simon, Jan;Mravec, Filip;Cvachovec, Frantisek
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3824-3832
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    • 2022
  • Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7-9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak.

Strategies to improve the range verification of stochastic origin ensembles for low-count prompt gamma imaging

  • Hsuan-Ming Huang
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3700-3708
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    • 2023
  • The stochastic origin ensembles method with resolution recovery (SOE-RR) has been proposed to reconstruct proton-induced prompt gammas (PGs), and the reconstructed PG image was used for range verification. However, due to low detection efficiency, the number of valid events is low. Such a low-count condition can degrade the accuracy of the SOE-RR method for proton range verification. In this study, we proposed two strategies to improve the reconstruction of the SOE-RR algorithm for low-count PG imaging. We also studied the number of iterations and repetitions required to achieve reliable range verification. We simulated a proton beam (108 protons) irradiated on a water phantom and used a two-layer Compton camera to detect 4.44-MeV PGs. Our simulated results show that combining the SOE-RR algorithm with restricted volume (SOE-RR-RV) can reduce the error of the estimation of the Bragg peak position from 5.0 mm to 2.5 mm. We also found that the SOE-RR-RV algorithm initialized using a back-projection image could improve the convergence rate while maintaining accurate range verification. Finally, we observed that the improved SOE-RR algorithm set for 60,000 iterations and 25 repetitions could provide reliable PG images. Based on the proposed reconstruction strategies, the SOE-RR algorithm has the potential to achieve a positioning error of 2.5 mm for low-count PG imaging.

SIMMER-IV application to safety assessment of severe accident in a small SFR

  • H. Tagami;Y. Tobita
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.873-879
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    • 2024
  • A sodium-cooled fast reactor (SFR) core has a potential of prompt criticality due to a change of core material distribution during a severe accident, and the resultant energy release has been one of the safety issues of SFRs. In this study, the safety assessment of an unprotected loss-of-flow (ULOF) in a small SFR (SSFR) has been performed using the SIMMER-IV computer code, which couples the models of space- and time-dependent neutronics and multi-component, multi-field thermal hydraulics in three dimensions. The code, therefore, is applicable to the simulations of transient behaviors of extended disrupted core material motion and its reactivity effects during the transition phase (TP) of ULOF, including a potential of prompt-criticality power excursions driven by fuel compaction. Several conservative assumptions are used in the TP analysis by SIMMER-IV. It was found out that one of the important mechanisms that drives the reactivity-inserting fuel motion was sodium vapor pressure resulted from a fuel-coolant interaction (FCI), which itself was non-energetic local phenomenon. The uncertainties relating to FCI is also evaluated in much conservative way in the sensitivity analysis. From this study, the ULOF characteristics in an SSFR have been understood. Occurrence of recriticality events under conservative assumptions are plausible, but their energy releases are limited.

카지미르 말레비치의 조형적 요소를 AI 프롬프트로 활용한 3D 디지털 패션디자인 연구 (A Study of 3D Digital Fashion Design Using Kazmir Malevich's Formative Elements as AI Prompt)

  • 이주영
    • 패션비즈니스
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    • 제28권3호
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    • pp.122-139
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    • 2024
  • Image-generated AI is rapidly emerging as a powerful tool to augment human creativity and transform the art and design process through deep learning capabilities. The purpose of this study was to propose and demonstrate the feasibility of a new design development method that combined traditional design methods and technology by constructing image-generated AI prompts based on artists' formative elements. The study methodology consisted of analyzing Kazmir Malevich's theoretical considerations and applying them to AI prompts for design, print pattern development, and 3D digital design. This study found that the suprematist works of Kazmir Malevich were suitable as design and print pattern prompts due to their clear geometric shapes, colors, and spatial arrangement. The AI-prompted designs and print patterns produced diverse results quickly and enabled an efficient design process compared to traditional methods, although additional refinement was required to perfect the details. The AI-generated designs were successfully produced as 3D garments, thereby demonstrating that AI technology could significantly contribute to fashion design through its integration with artistic principles. This study has academic significance in that it proposes a prompt composition method applicable to fashion design by combining AI and artistic elements. It also has industrial significance in that it contributes to design innovation and the implementation of creative ideas by presenting an AI-based design process that can be practically applied.