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- OHNUKI Akira
- Japan Atomic Energy Research Institute
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- AKIMOTO Hajime
- Japan Atomic Energy Research Institute
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- MURAO Yoshio
- Japan Atomic Energy Research Institute
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The applicability of the REFLA/TRAC code, which is one of best-estimate codes based on two-fluid model, was assessed for a typical small-break loss-of-coolant accident (SBLOCA) transient of PWR. The main assessment subject was to investigate whether the physical models in REFLA/TRAC can apply to the transient under SBLOCA condition (high pressure/low flow rate) or not. The applicability had been verified under low pressure/low flow rate condition during reflood phase in large-break LOCA transients of PWR. The assessment calculation was performed for Run SB-CL-05 (5% cold leg break SBLOCA test) in the ROSA-IV large-scale test facility. The REFLA/TRAC almost predicted the thermal-hydraulics in primary loops while the hydrau- lic models should be improved for regions at the pump side of loop seal and at the up-flow side of steam generator tube under CCFL condition. The core thermal-hydraulic models in REFLA/ TRAC give better prediction for core full-height differential pressure and the peak clad tem- perature (PCT) than those in original TRAC code. The PCT by the models in TRAC was lower about 100K than the measured one but the PCT by those in REFLA/TRAC was lower only about 40K.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 32 (3), 245-256, 1995
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
- 1390282679072801792
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- NII論文ID
- 10002072264
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK2MXksFymu78%3D
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- ISSN
- 18811248
- 00223131
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 使用不可