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36本プルトニウム燃料装荷炉心の冷却材喪失時ボイド反応度の測定: 25cmピッチ格子炉心実験データ集

Measurement of loss-of-coolant reactivity of two-region core using 36-rod plutonium fuel clusters

小綿 泰樹*; 清野 英昭*; 安保 昌徳*; 柴田 邦広*; 北山 一宏*

not registered; not registered; not registered; not registered; not registered

25cmピッチ正方格子をもつDCA炉心において,28本クラスタの1.2wt%濃縮UO/2燃料一様炉心およびその炉心の中央部9チャンネル(3$$times$$3チャンネル)を36本クラスタのPuO/2―UO/2燃料で置換した二領域炉心に関する冷却材喪失時ボイド反応度を臨界水位差法により測定した。ここで測定された冷却材喪失時ボイド反応度は,炉心内の全圧力管内の冷却材が喪失された場合および炉心中心の1本のみの圧力管内の冷却材が喪失された場合についてのものである。また,冷却材喪失前後における炉心内熱中性子束分布を銅ワイヤ放射化法により測定した。実験に使用した36本クラスタのプルトニウム燃料のプルトニウム富化度は0.54wt%または0.87wt%で,プルトニウム中の核分裂性プルトニウムの割合は約91%である。燃料棒直径は,約16.7mmでいわゆる太径のものである。なお,パラメータとして減速材重水中のボロン(ホウ素10)濃度を0および3.2ppmに選んだ。測定された冷却材喪失時ボイド反応度を,28本クラスタのプルトニウム燃料装荷炉心におけるボイド反応度およびWIMS-CITATIONコードによる予測計算値とともに下表に示す。この結果36本クラスタのプルトニウム燃料を炉心中央に部分装荷した炉心では,冷却材喪失時ボイド反応度を28本クラスタのプルトニウム燃料を装荷した場合に比べて,20$$sim$$30%負側へ移行させることが分った。また,36本クラスタ燃料装荷炉心における計算値は,実験値を70¢以内で再現する。

Loss-of-coolant reactivity of all channels and that of central channel have been measured in two-region core partially loaded with nine 36-rod PuO$$_{2}$$-UO$$_{2}$$ clusters. Lattice pitch is 25.0-cm throughout the core, and poison content in D$$_{2}$$O moderator is O or 3.2 ppm with $$^{10}$$B concentration. These 36-rod PuO$$_{2}$$-UO$$_{2}$$ clusters were placed in a central 3$$times$$3 channels of the core and the surrounding region was occupied with eighty-eight 28-rod 1.2 wt% enriched UO$$_{2}$$ clusters. Enrichment of plutonium in the 36-rod PuO$$_{2}$$-UO$$_{2}$$ fuel is 0.54 wt% or 0.87 wt%, and the fissile content in total plutonium of both PuO$$_{2}$$-UO$$_{2}$$ fuels is about 91 wt% (standard grade type Plutonium). Neutron flux distributions were also measured by $$gamma$$-counting of irradiated copper wire, in order to evaluate the change of neutron flux in the core before and after loss-of-coolant. Reactivities due to loss-of-coolant were obtained by integrating the level reactivity coefficient of moderator ($$sigma$$p/$$sigma$$H) of the perturbed core between the critical levels at the non-voided core and at the perturbed core. Values of ($$sigma$$p/$$sigma$$H) were obtained by converting doubling time of neutron flux due to small rise of moderator level ($$Delta$$H) to small reactivity($$Delta$$p). Experimental result of loss-of-coolant reactivities ($$rho$$$$_{o}$$$$rightarrow $$v) is tabled as below together with the ones of the core loaded with nine 28-rod PuO$$_{2}$$-UO$$_{2}$$ clusters and calculated values by WIMS-CITATION code. The measured $$rho$$$$_{o}$$ $$rightarrow $$v were determined within 50 ¢ of uncertainty. If PuO$$_{2}$$-UO$$_{2}$$ clusters were placed in the central 3 $$times$$ 3 channels of the core, 36-rod PuO$$_{2}$$-UO$$_{2}$$ clusters is more effective in shifting the $$rho$$$$_{o}$$ $$rightarrow $$ v to the negative side in comparison with 28-rod PuO$$_{2}$$-UO$$_{2}$$ clusters ; the nine 36-rod PuO$$_{2}$$-UO$$_{2}$$ clusters makes the $$rho$$$$_{o}$$ $$rightarrow $$ v ...

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