Renovation of epithermal neutron beam for BNCT at THOR by Liu, Y.-W.H, Huang, T.T, Jiang, S.H, Liu, H.M

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Depletion analysis on long-term operation of the conceptual Molten Salt Actinide Recycler & Transmuter (MOSART) by using a special sequence based on SCALE6/TRITON by Sheu, R.J., Chang, C.H., Chao, C.C., Liu, Y.-W.H.

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A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 production by Sheu, R.J., Chao, C.C., Feynberg, O., Liu, Y.-W.H.

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Characteristics of the new THOR epithermal neutron beam for BNCT by Tung, C.J, Wang, Y.L, Hsu, F.Y, Chang, S.L, Liu, Y-W.H

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Verification of the accuracy of BNCT treatment planning system THORplan by Li, H.S., Liu, Y.-W.H., Lee, C.Y., Lin, T.Y., Hsu, F.Y.

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Radiation shielding evaluation of the BNCT treatment room at THOR: A TORT-coupled MCNP Monte Carlo simulation study by Chen, A.Y., Liu, Y.-W.H., Sheu, R.J.

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A comparison of dose rate calculations for a spent fuel storage cask by using MCNP and SAS4 by Chen, A.Y., Chen, Y.F., Wang, J.N., Sheu, R.J., Liu, Y.-W.H., Jiang, S.H.

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BNCT for locally recurrent head and neck cancer: Preliminary clinical experience from a phase I/II trial at Tsing Hua Open-Pool Reactor by Wang, L.W., Wang, S.J., Chu, P.Y., Ho, C.Y., Jiang, S.H., Liu, Y.W.H., Liu, Y.H., Liu, H.M., Peir, J.J., Chou, F.I., Yen, S.H., Lee, Y.L., Chang, C.W., Liu, C.S., Chen, Y.W., Ono, K.

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Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods by Sheu, R. J., Chen, A. Y., Liu, Y.-W. H., Jiang, S. H.

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