Quantification of design margins/safety factors based on the prediction uncertainty in tritium production rate from fusion integral experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics
Conference
·
OSTI ID:197082
- Univ. of California, Los Angeles, CA (United States); and others
Various engineering-oriented fusion integral experiments were performed within the USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics during the last decade. The objectives of this ten-year program were: (a) to establish new experimental techniques for design-related neutronics experiments, (b) to provide experimental data on local and integrated parameters such as tritium production rate, nuclear heating, and activation for the purpose of assessing the accuracies of present nuclear data and calculational methods, and (c) to provide designers with design margin for important responses. Tritium breeding rate (TPR) has the prime focus among other reactions. The program consisted of three phases in which local and integrated measurements inside a Li{sub 2}O test assembly that has various engineering features of a prototypical blanket (e.g. SS FW, H{sub 2}O coolant channels, beryllium multiplier). The analysis of the experiments were performed independently by the US and JAERI using their own codes/databases. A wide range of the calculated-to-experimental (C/E) values were observed in all these experiments for local TPR from Li-6 (T{sub 6}), from Li-7 (T{sub 7}), and from Li-natural (T{sub n}). In this paper, the experimental and calculational data sets of local TPR in each experiment were interpreted to give estimate to the prediction uncertainty, u{sub i}, of the line-integrated TPR and its standard deviation, {sigma}{sub i}.
- OSTI ID:
- 197082
- Report Number(s):
- CONF-940664--
- Country of Publication:
- United States
- Language:
- English
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