Fuel and core design of super LWR with stainless steel cladding

Kazuhiro Kamei, Akifumi Yamaji, Yuki Ishiwatari, Liu Jie, Yoshiaki Oka

研究成果: Paper査読

22 被引用数 (Scopus)

抄録

An equilibrium core of High Temperature Supercritical-pressure Light Water Reactor, now called Super LWR, has been designed. The fuel assemblies loaded in the peripheral region of the core are cooled with descending flow to achieve a high average coolant core outlet temperature. In the present design, Stainless Steel is used for fuel rod claddings and for structural materials. Gd 2O3 concentration and the fuel load pattern are optimized to reduce fuel enrichment. Watts correlations are used for prediction of heat transfer in the core, which takes into account an improvement of heat transfer for downward flow, different from the Oka-Koshizuka correlation used in the previous design. It is found that the water rods with their downward flow need to be thermally insulated with thin ZrO2 layer to keep the moderator temperature below the pseudo critical temperature. As a result, an average coolant core outlet temperature of 500C is achieved. In addition, the effect of various heat transfer correlations on the cladding surface temperature is evaluated.

本文言語English
ページ2711-2720
ページ数10
出版ステータスPublished - 2005 12 1
外部発表はい
イベントAmerican Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 - Seoul, Korea, Republic of
継続期間: 2005 5 152005 5 19

Other

OtherAmerican Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05
CountryKorea, Republic of
CitySeoul
Period05/5/1505/5/19

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality

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