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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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Cs-137 sealed source found in Western Australia
A rendering of the sealed source capsule’s appearance. (Image: DFES)
Australian emergency services has located the lost sealed source, the BBC reported early February 1.
The caesium-137 capsule, part of a density gauge used at Rio Tinto’s Gudai-Darri mine in Western Australia, was found after a survey vehicle travelling at 70 km/h (43 mph) detected radiation, according to the report. According to Australia’s Department of Fire and Emergency Services, the capsule was located on the roadside of the Great Northern Highway, south of Newman. A serial number verified it was the lost source.
Last week, as reported yesterday by Nuclear Newswire, Australian authorities began searching 1,400 kilometers (870 miles) of Australia’s Great Northern Highway, between Perth and the remote town of Newman, for a lost sealed-source capsule containing cesium-137. The source was part of a density gauge used by mining company Rio Tinto at its mining operations in Western Australia.
Thursday, May 19, 2022|8:00–9:45AM EDT|Pointview
Michael L. Zerkle
Adam G. Nelson
John D. Bess
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Thermal Neutron Scattering Law Evaluations for Zirconium Carbide and Critical Mass Calculations
J.L. Wormald (Naval Nuclear Laboratory), J.C. Holmes (Naval Nuclear Laboratory), M.L. Zerkle (Naval Nuclear Laboratory)
Spectral Indices Measurements for Neutron Data Validation in the Lead - Bismuth VENUS-F Fast Cores for MYRRHA
A. Kochetkov (SCK CEN), A. Krása (SCK CEN), N. Messaoudi (SCK CEN), G. Vittiglio (SCK CEN), J. Wagemans (SCK CEN)
Measurement of U-233 Sample Reactivity Worth in KUCA for Integral Validation of Nuclear Data
Tadafumi Sano (Kindai Univ.), Jun-ichi Hori (Kyoto Univ.), Yoshiyuki Takahashi (Kyoto Univ.), Kazushi Terada (Kyoto Univ.), Hiroshi Yashima (Kyoto Univ.), Takashi Kanda (Kindai Univ.), Hironobu Unesaki (Kyoto Univ.)
Development of a Model to Estimate Resuspension of Fission Products in an Integral Pressurized Water Reactor Containment Vessel
Rohan Biwalkar (Pittsburgh Technical), Iza Lantgios (Univ. Pittsburgh), Sola Talabi (Pittsburgh Technical), Katherine Hornbostel (Univ. Pittsburgh)
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