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Monte Carlo calculations on transmutation of plutonium and minor actinides of pebble bed high temperature reactor

机译:卵石床高温反应器of和次act系元素trans变的蒙特卡洛计算

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The paper aimed to maximize the fuel burnup performance of plutonium and minor actinides fueled pebble bed high temperature reactor (PBMR-400). The PBMR-400 was designed as a reference core. The neutronic calculations were performed by the code combination MCNP-ORIGEN-MONTEBURNS. In this study, neutronic performances of three different types of nuclear fuels (Reactor Grade Plutonium -RGPu; Weapon Grade Plutonium - WGPu and Minor Actinides - MAs) combined with natural uranium were conducted in a PBMR-400 full core. The neutronic performances were compared with the original uranium fuel designed for this reactor. Neutronic calculations showed that 9.6 wt % enriched uranium has a core effective multiplication factor (k_(eff)) of 1.2395. Corresponding to this k_(eff) values the natural UO_2/ RG-PuO_2; natural UO_2/WG-PuO_2 and natural UO_2/MAO_2 mixture were found 70%/30%, 76%/24% and 63%/ 37%, respectively. The operation times were computed as ~2000, ~2500 and 1400 days whereas, the corresponding burnup values were obtained as ~163 000, ~194 000 and ~116 000 MWD/T, respectively, for end of life k_(eff) set equal to 1.08.
机译:本文旨在最大程度地提高of和次act系元素燃料的卵石床高温反应器(PBMR-400)的燃料燃烧性能。 PBMR-400被设计为参考核心。通过代码组合MCNP-ORIGEN-MONTEBURNS进行中子学计算。在这项研究中,三种天然核燃料(反应堆级core -RGPu;武器级P-WGPu和次Act系元素-MAs)与天然铀的中子性能在PBMR-400全芯中进行。将中子性能与为此反应堆设计的原始铀燃料进行了比较。中子学计算表明,9.6 wt%的浓缩铀的核心有效倍增系数(k_(eff))为1.2395。对应于该k_(eff)值,自然的UO_2 / RG-PuO_2;天然UO_2 / WG-PuO_2和天然UO_2 / MAO_2混合物的含量分别为70%/ 30%,76%/ 24%和63%/ 37%。计算得出的使用寿命为k_(eff)相等时,操作时间分别为〜2000,〜2500和1400天,而相应的燃耗值分别为〜163 000,〜194 000和〜116 000 MWD / T。到1.08。

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