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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
Takeshi Kase, Hideo Harada
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 59-70
Technical Paper | doi.org/10.13182/NSE97-A24457
Articles are hosted by Taylor and Francis Online.
The performance of a continuous neutron source using an electron accelerator was evaluated by computer simulation codes (EGS4 and MCNP) in terms of neutron yield, neutron flux distribution, neutron spectrum, and heat distribution. Electrons with energies from 10 to 100 MeV were injected into a tungsten converter in order to generate photons by bremsstrahlung. When the photon irradiated a heavy water (D2O) target, neutrons were produced by photonuclear reaction in the (D2O) target. This type of source was optimized for target geometry and electron energy from the point of neutron yield. The neutron spectrum was found to have two characteristic peaks, at the low-energy (thermal) region and the high-energy (million-electron-volt) region. The maximum photoneutrons per 1000 MeV of electron energy was 0.56 at the electron energy of 30 MeV. In the case of irradiation by a 30-MeV, 33-mA continuous electron beam, the maximum thermal neutron flux was on the order of 1011 cm−2·s−1.