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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
February 2024
Latest News
PG&E to dredge Diablo Canyon intake system
The owners of the Diablo Canyon nuclear power plant plan to dredge a massive buildup of shoaled sediment from its seawater intake cove.
Pacific Gas and Electric spokesperson Suzanne Hosn said, “The dredging project in the Diablo Canyon marina will remove approximately 70,000 cubic yards of sediment to prevent circumstances that could impact the power plant’s cooling system. Dredging will take place for the first time since operations began because of a rapid increase in sediment.”
M. Nishikawa, K. Munakata, T. Takeishi, A. Baba, T. Kawagoe, S. Beloglazov, N. Nakashima, K. Hashimoto, Yokoyama, K. Okuno, Y. Morimoto, H. Moriyama, K. Kawamoto
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1025-1029
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22739
Articles are hosted by Taylor and Francis Online.
Release curve of bred tritium from various ceramic breeder materials such as Li2ZrO3, Li2TiO3, and Li4SiO4 were obtained using the out-pile temperature programmed desorption method in the Kyoto University Research Reactor. A 0.4g sample of breeder particles contained in a quartz tube was irradiated for 120s at the thermal neutron flux of about 2.8x1017n/m2s in N2 atmosphere under the temperature of 360K. Tritium release behavior was measured using an ionization chamber connected to the release tritium measurement apparatus. The sample was purged by dry N2, N2 with hydrogen of various partial pressure, or humidified N2 gas. The temperature of the sample bed was changed linearly from room temperature to 1073K with the rising rate of 5K/min.Characteristics of tritium release behavior obtained for various ceramic breeder materials under various purge gas conditions are compared in this paper.