The thermal analysis of pre-defueled operation for decommissioning of a BWR4 reactor

Author:

Xiao Bo-Bin,Hsia Chen-Yuan

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference11 articles.

1. Boyd, C. F. (2000). Predictions of Spent Fuel Heatup After a Complete Loss of Spent Fuel Pool Coolant. NUREG-1726.

2. Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process;Chen;Ann. Nucl. Energy,2018

3. Code crosswalk of Fukushima-like simulations for Chinshan BWR/4 NPP using MELCOR2.1/SNAP, TRACE/SNAP, PCTRAN and MAAP5.03;Chiang;Nucl. Eng. Des.,2017

4. Collins, H. (2001). Technical Study of Spent. Fuel Pool Accident Risk at Decommissioning. NUREG-1738.

5. L.L. Humphries, R.K. Cole, D. L. L., V.G. Figueroa, & Young, M. F. (2015). MELCOR Computer Code Manuals.

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