検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 1 件中 1件目~1件目を表示
  • 1

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

Validation study in SAS4A code in simulated mild TOP condition

川田 賢一; 鈴木 徹

Transactions of the American Nuclear Society, 115(1), p.1597 - 1598, 2016/11

Model improvements and validation efforts for SAS4A code, which is the most advanced computer code for simulating the primary phase of the Core Disruptive Accident (CDA) of MOX-fueled Sodium-cooled Fast Reactors, have been performed utilizing the experimental data from the CABRI programs by JAEA, IRSN, CEA and KIT. In order to confirm validity of improved models of SAS4A, a systematic and comprehensive validation plan was defined. It was based on the PIRT (Phenomena Identification and Ranking Table) result for CDA of MOX-fueled fast reactors. This paper describes the preliminary result of validation study for SAS4A code in simulated Transient Over-Power (TOP) condition. The capability of the SAS4A code on the burst failure mode have been examined and validated under various TOP conditions for fuel pins with different irradiated conditions. This study enhanced the credibility of SAS4A code under a wider range of evaluation conditions than ever before.

1 件中 1件目~1件目を表示
  • 1