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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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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
Latest News
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
Y. Ikeda, A. Kumar, C. Konno, K. Kosako, Y. Oyama, F. Maekawa, H. Maekawa, M. Z. Youssef, M. A. Abdou
Fusion Science and Technology | Volume 28 | Number 1 | August 1995 | Pages 156-172
Technical Paper | Fusion Neutronics Integral Experiments — Part I / Blanket Engineering | doi.org/10.13182/FST95-A30404
Articles are hosted by Taylor and Francis Online.
Nuclear heat deposition rates in the structural components of a fusion reactor, have been measured directly with a microcalorimeter incorporated with an intense deuterium-tritium (D-T) neutron source, the Fusion Neutronics Source (FNS) at the Japan Atomic Energy Research Institute (JAERI), under the framework of the JAERI/U.S. Department of Energy (U.S. DOE) collaborative program on fusion neutronics. Structural materials of aluminum, titanium, iron, nickel, molybdenum, and Type 304 stainless steel, along with a ceramic of Li2CO3, have been studied with a small-size single probe configuration, subjecting them to D-T neutrons. Heat deposition rates at positions up to 200 mm of depth in a Type 304 stainless steel assembly bombarded with D-T neutrons were measured along with these single probe experiments. The measured heating rates were compared with comprehensive calculations in order to verify the adequacy of the currently available database relevant to the nuclear heating. In general, calculations with data of JENDL-3 and ENDL-85 libraries gave good agreement with experiments for all single probe materials, whereas RMCCS, based on ENDF/B-V, suffered from unreasonable overestimation in the heating number. For Li2CO3 with a low heat conduction coefficient, analysis was carried out by using a heat transfer calculation code ADINAT, coupled with the neutron and gamma-ray transport DOT3.5. It was demonstrated that the nuclear/thermal coupled calculation is a powerful tool to analyze the time-dependent temperature change due to the heat transfer in the probe materials. The analysis for the Type 304 stainless steel assembly, based on JENDL-3, demonstrated that the calculation, in general, was in good agreement with the measurement up to 200 mm of depth along the central axis of the assembly. The experimental approach demonstrated in this study clearly showed the feasibility of the calorimeter to measure the nuclear heating for the neutron field where the 14-MeV contribution is relatively small in comparison with the low-energy neutron contribution.
