• Title/Summary/Keyword: Neutron capture

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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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    • v.34 no.4
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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.

Development of evaluation of B/F benzothiazole analogues for boron neutron capture therapy

  • Ji-ung Yang;Soyeon Kim;Kyo Chul Lee;Yong Jin Lee;Jung Young Kim;Ji-Ae Park
    • Journal of Radiopharmaceuticals and Molecular Probes
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    • v.8 no.1
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    • pp.17-23
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    • 2022
  • Boron neutron capture therapy is a precision treatment technology that selectively destroys only tumor cells by irradiating thermal neutrons after accumulating boron drugs in tumor cells. Brain tumor is difficult to diagnose and treat due to the low permeability and targeting of drugs caused by the blood-brain-barrier. Crossing the BBB is essential for drug delivery to the brain. In this study, we designed and synthesized a novel compound incorporating benzothiazole to develop a boron drug with high BBB permeability and selectivity for brain tumor cells. In addition, their potential as a BNCT drugs was evaluated.

Measurement of the Energy-Dependent Neutron Capture Cross Section of $^{99}Tc$ by Using the Neutron TOF Method (-중성자 TOF법에 의한 $^{99}Tc$의 에너지의존 중성자 포획단면적측정-)

  • Yoon Jung-Ran;Lee Sang-Bock;Lee Jun-Haeng;Lee Sam-Yol
    • The Journal of the Korea Contents Association
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    • v.5 no.5
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    • pp.133-139
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    • 2005
  • The neutron capture cross section of $^{99}Tc$ has been measured relative to the $^{10}B(n,\gamma)$ standard cross section by the neutron time-of-flight(TOF) method in the energy range of 0.007 eV to 47 keV using a 46-MeV electron linear accelerator(linac) at the Research Reactor. Institute, Kyoto University(KURRI). In order to experimentally prove the result obtained, the supplementary cross section measurement has been made from 0.3 eV to 1 keV using the Kyoto University Lead stowing-down spectrometer (KULS) coupling to the linac. The relative measurement by the TOF method has been normalized to the reference value(20.01 b) at 0.0253 eV and the KULS measurement to that by the TOF method. The existing experimental data and the evaluated capture cross sections in ENDF/B-VI, JENDL-3.2, and JEF-2.2 have been compared with the current measurements by the linac TOF and the KULS experiments.

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Neutron Capture Elements in Meltal-poor Giants

  • Lee, Ye-Rim;Lee, Jae-Woo;Lee, Jeong-Deok;Lee, Ji-Na
    • Bulletin of the Korean Space Science Society
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    • 2008.10a
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    • pp.29.4-30
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    • 2008
  • We present elemental abundances of 12 red giants obtained with the BOAO 1.8m telescope and its fiber-fed echelle spectrograph. We perform the abundance analysis using the Kurucz model atmosphere and MOOG. Comparisons of our alpha- and neutron-capture elemental abundances and those in globular clusters and nearby dwarf galaxies will be presented.

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Epithermal Neutron Flux Enhancement Using SMA in Designing a Cf-Based Neutron Beam for BNCT

  • Kim, Do-Heon;Kim, Jong-Kyung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05a
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    • pp.937-942
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    • 1995
  • Great interest has prompted Boron Neutron Capture Therapy (BNCT) as a new treatment for brain tumors. The use of $^{252}$Cf as a neutron source for BNn makes the in-hospital treatments of tumors to be possible. Newly proposed subcritical multiplying assemblies (SMA) are explored to improve relatively tow neutron fluxes of the source and construct the feasibilities of $^{252}$Cf as a neutron source. The MCNP code has been used to evaluate the effective multiplication factor of the entire system and the intensities and percentages of epithermal neutron flux at the patient-end surface of the system. The neutron beam using SMA shows the epithermal neutron flux enhancement of about 13 times as large as the beam without using SMA. It is expected that the neutron beam proposed in this research will be more effective for treatment of tumors due to the increased therapeutic neutron fluxes.

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