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LLNL, Ampera partner to develop thorium-based TRISO fuel
Lawrence Livermore National Laboratory has formed a strategic partnership with Ampera to develop the company’s nuclear fuel concept through a project named THUNDER, for Thorium Unimodal Droplet Ejection for Reactors.
The focus of THUNDER is fabricating TRISO made with kernels of thorium rather than the usual uranium. LLNL and Ampera will evaluate and optimize liquid metal–jetting technology to produce highly uniform, spherical kernels of thorium-232 for later processing into TRISO fuel.
Dong H. Nguyen
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 80-91
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32509
Articles are hosted by Taylor and Francis Online.
A methodology has been constructed to assess the uncertainty in an output consequence calculated by a large code, due to the uncertainties in input data. A sensitivity analysis was first applied to the code to screen the input variables, leaving only those most affecting the output consequences. The variations of these effective inputs were prescribed by an effective combination of statistical designs, which accounted for the linear, quadratic, and two-factor interaction effects of the inputs on the calculated consequence. A key result of the methodology was the probability density function of the consequence of interest, expressed as a distribution of the Pearson family. The confidence level in calculating a consequence was readily obtained from this distribution function. The methodology was applied to the computer code MELT-IIIA, a major code for the analysis of the hypothetical core disruptive accident in liquidmetal fast breeder reactors, and the confidence level in predicting the time of initial pin failure during a transient overpower accident in the fast test reactor was determined. The sensitivity of this confidence level to the uncertainties of the input data was also shown, thereby establishing the need for well-documented statistical properties of data used in nuclear reactor safety analysis.