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題 名 | 直接輻射劑量分析程式之更新與標準運算程序之建立=The Study of Integrated Technique for Assessing Environmental Does at Site Boundary of Radioactive Waste Storage Installation |
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作 者 | 張柏菁; 張淑君; 施建樑; 陳英鑒; 許任玓; 江祥輝; 廖瑞鶯; 于蓓; 黃金益; | 書刊名 | 台電工程月刊 |
卷 期 | 616 1999.12[民88.12] |
頁 次 | 頁34-44 |
分類號 | 449.6 |
關鍵詞 | 直接輻射; 向天輻射; 點核仁法; 增建因數; Direct radiation; Skyshine; Point kernel method; Buildup factor; |
語 文 | 中文(Chinese) |
中文摘要 | 目前電廠評估放射性廢料貯存設施之廠界劑量,直接輻射採用QADCG/INER2 程 式,向天富射則採用SKYSHINE-Ⅲ 程式,惟其計算結果過於保守,故更新上述分析程式 且建立標準運算程序,使計算結果合理保守且更為精準。 於「直接輻射劑量分析程式之更新與標準運算程序之建立」計畫中,在放射性核種能譜 分析程式SPECTUM之更新方面,不但將程式轉置於個人電腦,並更新其核種數據檔,建 立多核種之其他、加馬能譜分析程式SPECTRUM-506 。而於點核仁法直接輻射劑量分析 程式QADCG/INER-2更新方面,參考美國國家標準ANSI/AND-6.43-1991 ,引進國外增 建因數建立程式ANS643 ,並將增建因數之GP擬合公式 植入QADCG/INER-2程式中, 完成新版QADCG/INER-3程式。在點核仁法直接輻射劑量分析程式QADCG/INER-3可信 度之驗證方面,利用蒙地卡羅法MCNP 程式針對美國國家標準ANSI/ANS-6.6.1-1987 之 參考計算問題進行可信度驗證,並探討QADCG/INER-3程式中各參數之選用標準。於放射 性廢料貯存設施廠界輻射劑量分析方面,針對核一廠壕溝、一號倉庫、一號倉庫、一號代用 倉庫等大型放射性廢料貯存設施進行廠界輻射劑量分析,包括直接輻射劑量分析以及向天輻 射劑量分析;同時依據上述之成果與使用經驗,建立一套放射性廢料貯存設施廠界輻射劑量 分析標準運算程序。 |
英文摘要 | Direct and skyshine dose has become critical issue in operating nuclear power plant recently since the day of large increase of the redwaste storage capacity requirement on site. Those doses are usually evaluated by QADCH/INER-2 code for direct dose and SKYSHINE-Ⅲ code for skyshine dose. The evaluation is over conservative. This project is to update the evaluation code package with adequate methodology and integrated analysis procedure establishment. Therefore, the doses can be calculated in reasonably conservative and accurate way. The revision is divided into three categories. First, SPECTRUM-506 is used to replace SPECTUM, in which nuclides databases are enlarged up to 506 and the operation is ported to PC. Secondly, we develop the QADCG/INER-3 code to replace QADCG/INER-2. The most important difference is the use of the geometric progression (GP) fitting function for t he gamma-ray buildup factor. It is well benchmarked by using the Monte Carlo code MCNP and sensitive parameters are investigated in detail. Thirdly, the analysis procedures are properly developed to fit Taiwan Power Company waste storage facilities. Finally, the dose of a waste storage of ChinShan unclear power plant is assessed using this code package and methodology. The results are verified in detail by using MCNP. |
本系統中英文摘要資訊取自各篇刊載內容。