1. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers
2. Hong H. and Joo H. G., “Analysis of the APR1400 PWR Initial Core with the nTRACER Direct Whole Core Calculation Code and the McCARD Monte Carlo Code,” Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18-19 (2017).
3. Hong H., Ban Y. S., Joo H. G., Salazar D. A., Franceschini F., “Analyses of AP1000® First Core with Direct Whole Calculation Codes,” Proceedings of the PHYSOR 2016, Sun Valley, Idaho, USA, May 1-5 (2016).
4. Ryu M., Cho H. H., Lim C. H., Jung Y. S., Joo H. G., “Preliminary Assessment of nTRACER and McCARD Direct Whole Core Transport Solutions to VERA Core Physics Benchmark Problems,” Transactions of the American Nuclear Society Winter Meeting, Anaheim, California, USA, Nov. 9-13 (2014).
5. Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code