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HTTRの1次加圧水冷却器の伝熱性能に関する評価

Evaluation of heat exchange performance for primary pressurized water cooler in HTTR

栃尾 大輔; 中川 繁昭

Tochio, Daisuke; Nakagawa, Shigeaki

定格熱出力30MWの高温工学試験研究炉(HTTR)では、原子炉で発生した熱を主冷却系を構成する加圧水冷却器,中間熱交換器による熱交換を経て、最終的に加圧水空気冷却器により大気に放散している。HTTRの主冷却系熱交換器は原子炉出口冷却材温度850$$^{circ}$$C/950$$^{circ}$$Cの条件下で原子炉で発生した30MWの除熱を行うための伝熱性能を有していなければいけない。本報では、HTTRにおいてこれまで実施してきた出力上昇試験,供用運転のデータから、主冷却系に設置されている熱交換器のうちの1次加圧水冷却器(PPWC)について伝熱性能を評価した。また、設計時におけるPPWCの伝熱性能との比較を行い、PPWCが設計時に要求された伝熱性能を有していることを確認した。

In High Temperature Engineering Test Reactor (HTTR), the rated thermal power of 30MW, the generated heat at reactor core is finally dissipated at the air-cooler by way of the heat exchangers of the primary cooling system, such as the primary pressurized water cooler (PPWC) and the intermediate heat exchanger (IHX). The heat exchangers in the primary cooling system are required the heat exchange performance to remove reactor generated heat 30MW under the condition of reactor coolant outlet temperature 850$$^{circ}$$C/950$$^{circ}$$C. Therefore, the heat exchanges are required to satisfy the design criteria of heat exchange performance. In this report, heat exchange performance data of the rise-to-power-up test and the in-service operation for the PPWC in the main cooling system was evaluated. Moreover, the evaluated values were compared with the design values, and it is confirmed that PPWC has the required heat exchange performance in the design.

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