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Abstrakt

Metal fuel is a promising candidate for the pyro-processed nuclear fuel, but the problem of loss of nuclear material due to the high reactivity of metal fuel and melting crucible in the metal fuel casting process must be solved for loss control and waste reduction. In this study, fabrication test was conducted to develop a new material NdYO3 as a new crucible material to improve the degree of anti-reactivity. The NdYO3 compact was manufactured by the CIP (Cold isostatic pressing) method with changing fraction of Nd2O3 and Y2O3 powders. Sintering process was performed at 1550°C for 10 hours. The systematic trends of XRD patterns shows that phase transformations form cubic structure to monoclinic structures occurred with the addition of Y2O3. The rate of pore were discussed with change of fraction of Nd2O3 and Y2O3.
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Autorzy i Afiliacje

Sang-Gyu Park
1
ORCID: ORCID
Ki-Hwan Kim
1
ORCID: ORCID
Jun Hwan Kim
1
ORCID: ORCID

  1. Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea

Abstrakt

LaYO3 which has phase stability at high temperature is introduced as a promising candidate for reaction-preventing crucible materials with Uranium-Zirconium (U-Zr) melt containing rare-earth elements (RE). RE is composed of rare-earth elements such as Nd, Ce, Pr and La. The LaYO3 material was synthesized by a solid-state reaction method at elevated temperature according to a pseudo-phase diagram of LaYO3 and Y2O3. Green compacts blended with La2O3 and Y2O3 powder were made by the Cold Isostatic Pressing (CIP) method, with La2O3 and Y2O3 powders varying with molar ratios from 1.0 to 1:2. LaYO3 synthetics were fabricated at sintering temperatures ranging from 1450°C to 1600°C. LaYO3 pellets sintered at below 1550°C showed a highly dense orthorhombic phase with a perovskite structure, resulting in an enhancing reaction-resistant effect with RE.
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Autorzy i Afiliacje

Ki-Hwan Ki
1
ORCID: ORCID
Yong-Wook Choe
2
Hoon Song
1
Sang-Gyu Park
1
ORCID: ORCID
Jun-Hwan Kim
1
ORCID: ORCID

  1. Korea Atomic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea
  2. Korea At omic Energy Research Institute, Next-Generation Fuel Technology Development Division, 989-111, Daedeok-daero, Yuseong-gu, Daejeon, 34057, Republic of Korea; Yonsei University, Department of Materials Science and Engineering, Seoul, 03722, South Korea

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