Experimental validation of a physics-based CRUD growth model using dedicated PWR loop tests
2025 · Nuclear Engineering and Technology
저자
Seungjin Seo, Yunju Lee, Ji Hyun Kim, Nakkyu Chae, Hee Sang Shim, Richard Ian Foster, 최성열 (Sungyeol Choi)
연구주제
Nuclear Engineering Thermal-Hydraulics · Nuclear reactor physics and engineering
NTIS 과학기술표준분류
에너지/자원만에너지·환경·원자력 확장
원자력 > 원자력안전기술 > 원전재료 경년열화 대처기술 및 기기/ 구조건전성 평가기술에너지 외
배정 근거: AI 키워드가 잡은 NTIS 과제의 분류(정책 연계 맵과 같은 방법).
AI 연구 키워드·방법
키워드 (OpenAlex)
pressurized water reactor sticking coefficient model validation sensitivity analysis
초록
The model previously developed to predict CRUD growth during the operation of PWRs was validated through the benchmark study for CRUD loop experiments. Because of the difference in the operation conditions between the CRUD loop and PWRs, there is a difference in the growth mechanism of the CRUD layer. Two CRUD loop experiments conducted in the UNIST and KAERI were selected as benchmark cases in this benchmark study. The model predicted similar growth behavior for the porous CRUD layer under the UNIST loop operating conditions, although there was a slight mismatch in the axial distribution and the deposition of the dense CRUD layer, which formed after the loop operation. In contrast, the model overestimated CRUD growth in the seven KAERI loop experiments when using the default sticking probability. A sensitivity study showed that reducing the sticking probability yielded better agreement …
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연구주제 1
Nuclear Engineering Thermal-Hydraulics