Post DNB Heat Transfer Experiments for PWR Fuel Assemblies
スポンサーリンク
概要
- 論文の詳細を見る
Nuclear Power Engineering Corporation (NUPEC) and Mitsubishi performed heat transfer experiments on post DNB (departure from nucleate boiling) for the pressurized water reactor (PWR) fuel assemblies under the sponsorship of the Japanese Ministry of Economy, Trade and Industry (METI) as one of a series of fuel assembly verification tests. Based on the obtained experimental data, a new evaluation model for the fuel rod heat transfer behavior after DNB was developed. A large safety margin, which had remained in the present thermal-hydraulic design that did not allow DNB, was confirmed by applying the developed model to the PWR plant safety analysis.
- 社団法人 日本原子力学会の論文
- 2003-10-25
著者
-
SUEMURA Takayuki
Mitsubishi Heavy Industries, Ltd.
-
Suemura Takayuki
Mitsubishi Heavy Industries Ltd.
-
TSUKUDA Yoshiaki
Nuclear Power Engineering Corporation
-
KONO Norio
Nuclear Power Engineering Corporation
-
AKIYAMA Yoshiei
Mitsubishi Heavy Industries, Ltd.
-
HORI Keiichi
Mitsubishi Heavy Industries, Ltd.
-
Hori Keiichi
Mitsubishi Heavy Industries Ltd.
-
Akiyama Yoshiei
Mitsubishi Heavy Industries Ltd.
関連論文
- Analysis of the Main Steam Line Break Benchmark (Phase II) Using ANCK/MIDAC Code
- Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method
- The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems
- Post DNB Heat Transfer Experiments for PWR Fuel Assemblies
- On Ripple of Annular Two-Phase Flow : 1. Statistical Characteristics of Ripples