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Uranium integral fission product yields for a spectrally-shaped 14.1 MeV neutron source at the National Ignition Facility
Applied Radiation and Isotopes ( IF 1.6 ) Pub Date : 2021-04-03 , DOI: 10.1016/j.apradiso.2021.109711
N. Quartemont , N. Gharibyan , K. Moody , J.E. Bevins

This paper describes the experimental results for an energy tuning assembly created to modify the National Ignition Facility deuterium–tritium fusion neutron source into a notional thermonuclear and prompt fission neutron spectrum, which has applications in integral measurements, nuclear data benchmarks, and radiation effects on microelectronics. The Monte Carlo neutron transport utilized MCNP5 to estimate the ETA-modified fluence using the ENDF-B/VIII.0 and IRDFF-II continuous energy nuclear data libraries, and SCALE Sampler was used to estimate the systematic nuclear data covariance using ENDF-B/VII.1 and IRDFF-II in a 252-group structure. The experiment fielded eight activation foils and a highly enriched uranium sample. This provided fifteen reaction channels that were used in a forward-fit comparison to the modeled results and to unfold the neutron spectrum using STAYSL. Gamma-ray spectrometry was performed on the activation and highly enriched uranium foils, and the reduced χ2 between the modeled and experimental values was 1.21. The results from the STAYSL unfold, reduced χ2=1.62, indicated that the modeled neutron spectrum was achieved and the systematic nuclear data uncertainty associated with the neutron transport and activation product cross sections was representative of the experiment. Integral cumulative fission product yield data were collected for 37 mass chains with a combination of gamma-ray spectrometry and radiochemical analysis. Fission product analysis was generally in agreement with two models using a semi-empirical fit and the General Observables of Fission code, with the exception of mass chains 88, 109, 111, 112, 113, 129, 139, 142, 144, 151, and 156.



中文翻译:

国家点火设施的光谱形14.1 MeV中子源的铀积分裂变产物

本文介绍了一个能量调谐组件的实验结果,该组件的创建是将国家点火设施氘-聚变中子源修改为名义上的热核和裂变中子谱,该谱在积分测量,核数据基准以及对微电子的辐射效应中具有应用。蒙特卡洛中子传输利用MCNP5使用ENDF-B / VIII.0和IRDFF-II连续能量核数据库估算ETA修饰的通量,而SCALE Sampler用于使用ENDF-B / B估算系统核数据协方差VII.1和IRDFF-II为252组结构。该实验部署了八个活化箔和一个高度浓缩的铀样品。这提供了15个反应通道,这些通道用于与模型结果进行正向拟合比较,并使用STAYSL展开中子谱。对活化的和高度浓缩的铀箔进行了伽马射线光谱分析,χ2个之间的模型值和实验值为1.21。来自STAYSL的结果得以展开,减少了χ2个=1个62,表明已达到建模的中子谱,并且与中子传输和活化产物横截面相关的系统核数据不确定性是该实验的代表。结合伽马射线光谱法和放射化学分析,收集了37条质量链的累积累积裂变产物产量数据。除了质量链88、109、111、112、113、129、139、142、144、151,和156。

更新日期:2021-04-11
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