• 제목/요약/키워드: wave fission

검색결과 4건 처리시간 0.021초

해양장파의 증폭과 변형에 대한 연구 (A Study on Amplification and Deformation of Long-Period Waves)

  • 배재석;신충훈;조영준;윤성범
    • 한국수자원학회:학술대회논문집
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    • 한국수자원학회 2011년도 학술발표회
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    • pp.45-49
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    • 2011
  • 본 연구에서는 일본 전력중앙연구소에서 수행된 wave fission 수리모형실험 자료를 토대로 일차원 FUNWAVE 수치모형을 이용하여 wave fission 현상을 재현하는 수치모의를 수행하였다. FUNWAVE 수치모형은 Boussinesq 방정식을 지배방정식으로 사용하고 있으며 파의 분산효과와 비선형 효과를 고려할 수 있는 수치모형이다. 따라서 wave fission의 주된 발생원인인 분산효과와 비선형효과에 대한 고려를 통해 수치모의 결과는 수리모형실험의 관측치와 상당히 잘 일치함을 확인할 수 있었다. 또한, 본 연구에서는 추가적으로 해수의 흐름이 존재하는 경우를 가정하고 수로 내 일정한 유량의 흐름을 추가하여 wave fission 일차원 수치모의를 수행하였다. 수치모의 결과 파의 진행방향과 반대방향으로 흐름이 존재하는 경우 wave fission으로 인한 수면변위의 크기가 상대적으로 증가함을 확인할 수 있었으며 반대로 파의 진행방향과 동일한 방향으로 흐름이 존재하는 경우 wave fission으로 인한 수면변위의 크기가 상대적으로 감소함을 확인할 수 있었다.

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Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

  • Bedenko, Sergey V.;Arzhannikov, Andrey V.;Lutsik, Igor O.;Prikhodko, Vadim V.;Shmakov, Vladimir M.;Modestov, Dmitry G.;Karengin, Alexander G.;Shamanin, Igor V.
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.1736-1746
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    • 2021
  • The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was based on the concept of a high-temperature gas-cooled thorium reactor core. The second block was an axially symmetrical extended plasma generator of additional neutrons that was placed in the near-axial zone of the facility blanket. The calculated models of the blanket and the plasma generator of D-T neutrons created within the work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodic operation modes. This research will make it possible to construct a safe facility and investigate the properties of thorium fuel, which can be continuously used in the epithermal spectrum of the considered hybrid fusion-fission reactor.

Neutron Cross Section Evaluation on Mo-95, Tc-99, Ru-101 and Rh-1()3 in the Fast Energy Region

  • Lee, Y. D.;J. H. Chang
    • Nuclear Engineering and Technology
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    • 제34권6호
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    • pp.533-544
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    • 2002
  • The neutron induced nuclear data for Mo-95, Tc-99, Ru-101 and Rh-103 was calculated and evaluated in the fast energy region. The energy dependent optical model potential parameters were extracted based on the recent experimental data and applied up to 20 MeV. The s-wave strength function was calculated from the parameters. Spherical optical model, statistical model in equilibrium energy, multistep direct and multistep compound model in pre-equilibrium energy and direct capture model were used in the calculation. The theoretically calculated cross sections were compared with the experimental data and the evaluated files The model- calculated total and capture cross sections were in good agreement with the reference experimental data. The direct capture contribution improved the capture cross sections in pre- equilibrium region. The evaluated cross section results were compiled to ENDF-6 format and will improve the ENDF/B-Vl.

Neutron Cross Section Evaluation on Pr-141, Nd-143, Nd-145, Sm-147 and Sm-149

  • Lee, Y. D.;J. H. Chang
    • Nuclear Engineering and Technology
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    • 제34권4호
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    • pp.370-381
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    • 2002
  • The neutron induced nuclear data for Pr-141, Nd-143, Nd-145, Sm-147 and Sm-149 were calculated and evaluated from 10 keV to 20 MeV. The energy dependent optical model potential parameters were extracted based on the recent experimental data and applied up to 20 MeV. The s-wave strength function was calculated. Spherical optical model , statistical model in equilibrium energy, multistep direct and multistep compound model in pre-equilibrium energy and direct capture model were introduced in Empire calculation. The theoretically calculated cross sections were compared with the experimental data and the evaluated files. The model calculated total and capture cross sections were in good agreement with the reference experimental data. The capture cross sections in pre-equilibrium were enhanced in recent released Empire version. The evaluated cross section results were compiled to ENDF-6 format and will improve the ENDF/B-Vl.