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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.
Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 617-627
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT85-A33684
Articles are hosted by Taylor and Francis Online.
Measurements of thermal and nonthermal neutron streaming were taken throughout the medical irradiation room and the two-legged labyrinth of the Musashi Institute of Technology Research Reactor (the Musashi reactor) by using a rem counter. The length of the measured line was 8 m. The measurements were also analyzed by using the Monte Carlo coupling technique. The contribution of nonthermal neutrons was obtained with a cadmium-covered rem counter and that of thermal neutrons was obtained from the difference between the responses measured with and without the cadmium cover. The response ratio of total neutrons to nonthermal neutrons is constant for the straight part of the duct and increases rapidly around the bent portion. The constant values of the response ratio are 2, 3, and 5 for the first, second, and third legs, respectively. The value of 1.5 count / s = 1 mrem / h was used as the coefficient for conversion to the neutron dose rate. The discrepancies between the measured and calculated results are within ∼50% for the nonthermal neutron response, and within a factor of 2 for total neutron response. The fractional standard deviations of the Monte Carlo calculations are 0.07 to 0.12 and 0.13 to 0.24 in the first leg, 0.07 to 0.18 and 0.13 to 0.44 in the second leg, and 0.12 to 0.38 and 0.17 to 0.56 in the third leg for nonthermal and total neutron dose rates, respectively.