• 제목/요약/키워드: OpenMC

검색결과 113건 처리시간 0.019초

Valve actuation effects on discrete monopropellant slug delivery in a micro-scale fuel injection system

  • McDevitt, M. Ryan;Hitt, Darren L.
    • Advances in aircraft and spacecraft science
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    • 제1권4호
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    • pp.409-425
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    • 2014
  • Converging flows of a gas and a liquid at a microchannel cross junction, under proper conditions, can result in the formation of periodic, dispersed microslugs. This microslug formation phenomenon has been proposed as the basis for a fuel injection system in a novel, 'discrete' monopropellant microthruster designed for use in next-generation miniaturized satellites. Previous experimental studies demonstrated the ability to generate fuel slugs with characteristics commensurate with the intended application during steady-state operation. In this work, numerical and experimental techniques are used to study the effect of valve actuation on slug characteristics, and the results are used to compare with equivalent steady-state slugs. Computational simulations of a valve with a 1 ms valve-actuation cycle show that as the ratio of the response time of the valve to the fully open time is increased, transient effects can increase slug length by up to 17%. The simulations also demonstrate that the effect of the valve is largely independent of surface tension coefficient, which is the thermophysical parameter most responsible for slug formation characteristics. Flow visualization experiments performed using a miniature valve with a 20 ms response time showed less than a 1% change in the length of slugs formed during the actuation cycle. The results of this study indicate that impulse bit and thrust calculations can discount transient effects for slower valves, but as valve technology improves transient effects may become more significant.

Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method

  • Li, Yunzhao;He, Qingming;Cao, Liangzhi;Wu, Hongchun;Zu, Tiejun
    • Nuclear Engineering and Technology
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    • 제48권2호
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    • pp.339-350
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    • 2016
  • Based on the resonance integral (RI) tables produced by the NJOY program, the conventional subgroup method usually ignores both the resonance elastic scattering and the resonance interference effects. In this paper, on one hand, to correct the resonance elastic scattering effect, RI tables are regenerated by using the Monte Carlo code, OpenMC, which employs the Doppler broadening rejection correction method for the resonance elastic scattering. On the other hand, a fast resonance interference factor method is proposed to efficiently handle the resonance interference effect. Encouraging conclusions have been indicated by the numerical results. (1) For a hot full power pressurized water reactor fuel pin-cell, an error of about +200 percent mille could be introduced by neglecting the resonance elastic scattering effect. By contrast, the approach employed in this paper can eliminate the error. (2) The fast resonance interference factor method possesses higher precision and higher efficiency than the conventional Bondarenko iteration method. Correspondingly, if the fast resonance interference factor method proposed in this paper is employed, the $k_{inf}$ can be improved by ~100 percent mille with a speedup of about 4.56.

Limits on the efficiency of event-based algorithms for Monte Carlo neutron transport

  • Romano, Paul K.;Siegel, Andrew R.
    • Nuclear Engineering and Technology
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    • 제49권6호
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    • pp.1165-1171
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    • 2017
  • The traditional form of parallelism in Monte Carlo particle transport simulations, wherein each individual particle history is considered a unit of work, does not lend itself well to data-level parallelism. Event-based algorithms, which were originally used for simulations on vector processors, may offer a path toward better utilizing data-level parallelism in modern computer architectures. In this study, a simple model is developed for estimating the efficiency of the event-based particle transport algorithm under two sets of assumptions. Data collected from simulations of four reactor problems using OpenMC was then used in conjunction with the models to calculate the speedup due to vectorization as a function of the size of the particle bank and the vector width. When each event type is assumed to have constant execution time, the achievable speedup is directly related to the particle bank size. We observed that the bank size generally needs to be at least 20 times greater than vector size to achieve vector efficiency greater than 90%. When the execution times for events are allowed to vary, the vector speedup is also limited by differences in the execution time for events being carried out in a single event-iteration.

Role of Intergenic and 3'-Proximal Noncoding Regions in Coat Protein Expression and Replication of Barley yellow dwarf virus PAV

  • Moon, Jae-Sun;Nancy K. McCoppin;Leslie L. Domier
    • The Plant Pathology Journal
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    • 제17권1호
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    • pp.22-28
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    • 2001
  • Barley yellow dwarf virus PAV (BYDV-PAV) has a 5.7-kb positive-sense single-stranded RNA genome that contains six open reading frames (ORFs). BYDV-PAV produces three subgenomic RNAs (sgRNAs). The largest of which encodes the coat, 17-kDa, and readthrough proteins from two initiation codons. To investigate the role of intergenic and 3'-proximal noncoding regions (NCRs) in coat protein (CP) expression and BYDV-PAV replication, a full-length infectious cDNA of the RNA genome of an Illinois isolate of BYDV-PAV was constructed downstream of the Cauliflower mosaic virus-35S promoter. Linear DNA molecules of these cDNAs were infectious, expressed the 22-kDa CP, and produced both genomic RNA sgRNAs in ratios similar to those observed in protoplasts inoculated with viral RNA. The portion of 5'NCR of sgRNA1 between ORFs 2 and 3 was not required for, but enhanced translation of CP from ORF3. Mutants containing deletions in the NCR downstream of ORF5 failed to replicate in oat protoplasts. These results indicate that an intact 3$^1$NCR is required for BYDV-PAV replication.

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Improvement and verification of the DeCART code for HTGR core physics analysis

  • Cho, Jin Young;Han, Tae Young;Park, Ho Jin;Hong, Ser Gi;Lee, Hyun Chul
    • Nuclear Engineering and Technology
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    • 제51권1호
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    • pp.13-30
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    • 2019
  • This paper presents the recent improvements in the DeCART code for HTGR analysis. A new 190-group DeCART cross-section library based on ENDF/B-VII.0 was generated using the KAERI library processing system for HTGR. Two methods for the eigen-mode adjoint flux calculation were implemented. An azimuthal angle discretization method based on the Gaussian quadrature was implemented to reduce the error from the azimuthal angle discretization. A two-level parallelization using MPI and OpenMP was adopted for massive parallel computations. A quadratic depletion solver was implemented to reduce the error involved in the Gd depletion. A module to generate equivalent group constants was implemented for the nodal codes. The capabilities of the DeCART code were improved for geometry handling including an approximate treatment of a cylindrical outer boundary, an explicit border model, the R-G-B checker-board model, and a super-cell model for a hexagonal geometry. The newly improved and implemented functionalities were verified against various numerical benchmarks such as OECD/MHTGR-350 benchmark phase III problems, two-dimensional high temperature gas cooled reactor benchmark problems derived from the MHTGR-350 reference design, and numerical benchmark problems based on the compact nuclear power source experiment by comparing the DeCART solutions with the Monte-Carlo reference solutions obtained using the McCARD code.

NTP-ERSN verification with C5G7 1D extension benchmark and GUI development

  • Lahdour, M.;El Bardouni, T.;El Hajjaji, O.;Chakir, E.;Mohammed, M.;Al Zain, Jamal;Ziani, H.
    • Nuclear Engineering and Technology
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    • 제53권4호
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    • pp.1079-1087
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    • 2021
  • NTP-ERSN is a package developed for solving the multigroup form of the discrete ordinates, characteristics and collision probability of the Boltzmann transport equation in one-dimensional cartesian geometry, by combining pin cells. In this work, C5G7 MOX benchmark is used to verify the accuracy and efficiency of NTP-ERSN package, by treating reactor core problems without spatial homogenization. This benchmark requires solutions in the form of normalized pin powers as well as the vectors and the eigenvalue. All NTP-ERSN simulations are carried out with appropriate spatial and angular approximations. A good agreement between NTP-ERSN results with those obtained with OpenMC calculation code for seven energy groups. In addition, our studies about angular and mesh refinements are carried out to produce better quality solution. Moreover, NTP-ERSN GUI has also been updated and adapted to python 3 programming language.

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%.

경비골, 슬개골 동시 골절된 소아마비 후유증 환자에 대한 한방복합치료 1례 (The Effect of Complex Korean Medical Treatment for Tibia, Fibula and Patellar Fractures in Patient with Sequelae of Poliomyelitis: A Case Report)

  • 김채영;최지수;안희덕
    • 한방재활의학과학회지
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    • 제34권2호
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    • pp.173-180
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    • 2024
  • Objectives The purpose of this study is to report the effects of Korean medicine treatment on tibia, fibula, and patellar fractures with sequelae of poliomyelitis. Methods A 64-year-old male patient was treated with acupuncture, herbal medicine, cupping, moxibustion, and exercise treatment for 59 days after open reduction and internal fixation and tension band wiring surgery. The effects were evaluated using a visual analog scale (VAS), manual muscle testing (MMT), range of motion (ROM), Western Ontario and McMaster Universities (WOMAC), and EuroQol-5 dimension (EQ-5D) index. Results After treatment, VAS decreased from 7 to 2. MMT, ROM, WOMAC, EQ-5D and walking ability were improved. Conclusions This case study suggests that Korean medicine treatment could be effective for tibia, fibula, patellar fractures in patients with sequelae of poliomyelitis.

중대사고시 노심용융물의 Rayleigh-Benard 자연대류 예비 실험 (A Preliminary Experiment for Rayleigh-Benard Natural Convection for Severe Accident Condition)

  • 문제영;정범진
    • 에너지공학
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    • 제21권3호
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    • pp.254-264
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    • 2012
  • 원자력발전소 중대사고시 노심용융물의 Rayleigh-Benard 자연대류 문제에 대한 예비실험으로 두 평판 사이의 거리, 측면벽의 유무 및 평판의 기하구조가 열전달에 미치는 영향에 대해 실험적 연구를 수행하였다. 열전달 실험을 대신하여 상사성의 원리를 이용한 황산-황산구리 수용액의 전기도금계를 물질전달계로 채택하였다. 실험은 $Ra_s$$1.06{\times}10^7{\sim}2.91{\times}10^{10}$의 범위에서 실험적 조건을 변화시켜가며 열전달을 측정하였다. 실험결과 단일 수평평판에서 측정한 열전달은 McAdams의 수평평판 자연대류 열전달 상관식과 일치하였고 두 평판에서 측정한 열전달은 Dropkin과 Somerscales, Globe와 Dropkin의 Rayleigh-Benard 자연대류 열전달 상관식과 매우 유사한 경향을 보였다. 두 평판 사이의 거리가 작을 경우 열전달이 높다가 거리가 증가하면 단일 수평평판에서의 자연대류 열전달과 같아졌다. 평판에 설치된 휜(Fin)은 열전달을 향상시켰다. 모든 경우에서 측면벽이 없는 경우의 열전달이 측면 벽이 있는 경우보다 항상 높았다.

마산 각섬석-흑운모 화강암의 연령: 후기 백악기 정치연령 (The Late Cretaceous Emplacement Age of Masan Hornblende-Biotite Granite)

  • 이태호;박계헌;김정민;김명정
    • 암석학회지
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    • 제26권1호
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    • pp.1-11
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    • 2017
  • 백악기 경상분지 남부의 마산 각섬석-흑운모 화강암의 정치연령을 규명하기 위하여 K-Ar, Ar-Ar 및 U-Pb 연대측정을 수행하였다. 각섬석 K-Ar 연대측정으로 구한 약 108 Ma의 연령은 이전에 보고된 Rb-Sr 연령과 비슷하다. 그러나 단입자 전용융으로 구한 각섬석 $^{40}Ar/^{39}Ar$ 연대측정 결과는 분산이 심하여 의미있는 연령을 구할 수 없었으며 이는 각섬석의 변질에 의한 동위원소계의 교란영향으로 평가된다. 따라서 동일 암석에서 분리한 각섬석에 대한 K-Ar 연대측정 결과 역시 신뢰하기 어렵다. 흑운모에 대한 단입자 전용융 $^{40}Ar/^{39}Ar$ 연대측정 결과는 평균 $75.8{\pm}3.0Ma$의 결과가 구해졌으며, 젊은 쪽으로 분산되는 45-75 Ma 범위의 값을 제거하면 약 80 Ma의 연령이 산출된다. 한편 SHRIMP와 LA-MC-ICPMS로 저어콘에 대한 U-Pb 연대측정을 수행하여 구한 마산 각섬석-흑운모 화강암의 정치연령은 각각 $87.6{\pm}2.7Ma$$86.8{\pm}0.4Ma$이다. 약 80 Ma의 흑운모 $^{40}Ar/^{39}Ar$ 연령은 마산 각섬석-흑운모 화강암의 냉각연령을 반영하는 것이거나 또는 주변에서 일어난 경상분지 내의 강한 화성활동에 의한 열적 교란의 영향일 수 있다.