Dany Mulyana is a current Ph.D. student working with Dr. Chirayath on developing an integrated risk analysis of the High Temperature Gas Reactor (HTGR) by using Monte Carlo-N Particles (MCNP) code to run an exhaustive reactor physics calculation simulating an online refueling of a generation IV reactor. He developed a code to generate the necessary inputs for MCNP and to analyze its outputs, mostly the produced isotopes content needed to conduct the proliferation risk analysis using multi-attribute analysis. Each monte carlo simulation for the reactor physics problem requires at least 440 computer hours which has to be run for at least 500 sets of simulation. He is interested in coupling the proliferation risk analysis with the economics risk analysis of the entire HTGR’s fuel cycle to provide a policy and decision framework needed for any stakeholders, especially countries looking for an economic and peaceful nuclear energy program. The study would cover strategic methodology and systemic framework to minimize both economic and proliferation risks in choosing HTGR as the transmuter technology. Mulyana received his Bacelor’s degree in Physics from Universitas Padjadjaran, Indonesia in 2003 and his Master???s degree in Physics from Universitas Indonesia in 2007. He has spent 14 years working as a nuclear system engineer for Indonesian Nuclear Energy Agency.
- D. Mulyana, S.S. Chirayath, "Investigation of Nuclear Safeguards Attributes Through Neutronics Simulation of Pebble Bed Reactor Core", 2019 ANS Winter Meeting and Nuclear Technology Expo, Washington, D.C., 17 – 21 November 2019.
- M.M. Mendoza, A.A. Sagadevan, J.N. Wagner, S.S. Chirayath, E.D. Kitcher, H. Rysz, L. Anuar, A. Perry, A. Maldonado, M. Ramirez, D. Mulyana, A. Edwin, and S. Martinson, "Advanced Reactor Safeguards Workshop at Texas A&M University", Poster. 60th Annual Meeting of the Institute for Nuclear Materials Management (INMM), Palm Desert, California, 14-18 July 2019.
- D. Mulyana S.S. Chirayath, "Nonproliferation Challenges within High Temperature Gas Reactor Fuel Cycles", presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018.