書誌事項
- タイトル別名
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- Study on Effect of Local Power Distribution of Fuel Assembly on Critical Power of Reduced-Moderation Water Reactor (RMWR)
- テイゲンソク ケイスイロ ノ ネンリョウ シュウゴウタイ キョクショ シュツリョク ブンプ ノ ゲンカイ シュツリョク エ ノ エイキョウ ヒョウカ
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A reduced-moderation water reactor (RMWR) is an innovative light water reactor comprising tight-lattice fuel assemblies with a gap clearance of around 1.0 mm for a reduction in water volume ratio to achieve a high conversion ratio. By taking into account recent experimental findings from 37-rod tight-lattice bundle thermal-hydraulic tests indicating that the critical power tends to be higher for a peripheral peak local power distribution than for a flat power distribution, the viability of fuel assembly designs with fewer types of plutonium enrichment of MOX fuel, which may result in a large local peaking factor in peripheral rods, was assessed in this report. Critical powers of 217-rod bundles with peripheral peaks for upper and lower MOX regions of the double-flat core of the RMWR were calculated by a subchannel analysis code NASCA. Peripheral peaking with the corresponding local peaking factor for a uniform plutonium enrichment design yields almost the same critical power as that for a flat power distribution. Thus, a reduction in fuel fabrication burden may be possible by decreasing the number of types of plutonium fuel enrichment while maintaining the same thermal-hydraulic margin as the fuel assembly design with five enrichment types of MOX fuel.<br>
収録刊行物
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- 日本原子力学会和文論文誌
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日本原子力学会和文論文誌 9 (2), 139-149, 2010
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001205187550976
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- NII論文ID
- 10026451753
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- NII書誌ID
- AA11643165
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- ISSN
- 21862931
- 13472879
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- NDL書誌ID
- 10724489
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- NDL
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- 使用不可