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題 名 | Neutron Transmission Through Structural Pipes Using Monte Carlo Technique=利用蒙地卡羅技術探討中子經由結構管道之傳輸現象 |
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作 者 | Khan,Rao F. H.; Baig,Shahid; Ahmad,N.; | 書刊名 | 核子科學 |
卷 期 | 36:5 1999.10[民88.10] |
頁 次 | 頁309-315 |
分類號 | 339.413 |
關鍵詞 | 蒙地卡羅技術; 中子; 結構管道; 傳輸; MTR; Monte Carlo technique; MCNP; Neutron transport; Auxiliary piping; Ray analysis method; Simon-clifford equation; Ducts; |
語 文 | 英文(English) |
英文摘要 | In MTR type research reactors, the core is hanging in a pool of water from a bridge with structural pipes. The housings of the detectors also consist of hollow pipes. The nuclear radiation such as neutrons and gamma rays can stream through these hollow pipes and can deliver lethal dose at the bridge. It is therefore necessary to calculate the amount of radiation streaming through these pipes. For the purpose of estimating the dose at the bridge due to fast neutrons, a computer code NTAP has been developed. The code is written in FOR-TRAN-77 programming language and it uses analog Monte Carlo simulation to account for fast neutron transport through the empty auxiliary pipe. The core is optimized by selecting it either as a point source or a disk with fission neutron energy distribution. The results of simulation show that neutrons contributing to dose at the bridge are those streaming directly and those, which arrive after multiple scattering in surrounding water. The albedo of water was also verified by this code. Point-wise cross-section library ENDF/B-VI was used for multiple ple scattering in water around pipe. For a 1O-m long and 7-cm diameter guide tube almost 99.9% contribution comes from direct streaming. The results are in good agreement with MCNP and with ray analysis technique. |
本系統中英文摘要資訊取自各篇刊載內容。