2010
DOI: 10.3327/jnst.47.684
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Study of the Self-Controllability for the Fast Reactor Core with High-Thermal-Conductivity Fuel

Abstract: The tolerance capability against ATWS for the FBR core with metallic fuel can be improved by employing a fuel with high thermal conductivity (HTC fuel) instead of the conventional metallic fuel, U-Pu-Zr. To investigate the self-controllability for the HTC-fueled core with U-Pu-Al alloy fuel, having one order of magnitude higher thermal conductivity than that of the U-Pu-Zr, the core employing the U-Pu-Al fuel was evaluated against ULOF and UTOP. Based on the systematic calculation, it was found that the larger… Show more

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“…Also, aluminum's low neutron cross section [23] precludes significant neutron interactions during nuclear fuel operation and storage. In fact, fuels directly incorporating aluminum for, among other advantages, improved thermal conductivity have been previously investigated [24,25]. Helium transport properties in alumina can be understood with complementary data such has been previously obtained by van Veen [19] and Hurst [26].…”
Section: Introductionmentioning
confidence: 96%
“…Also, aluminum's low neutron cross section [23] precludes significant neutron interactions during nuclear fuel operation and storage. In fact, fuels directly incorporating aluminum for, among other advantages, improved thermal conductivity have been previously investigated [24,25]. Helium transport properties in alumina can be understood with complementary data such has been previously obtained by van Veen [19] and Hurst [26].…”
Section: Introductionmentioning
confidence: 96%