FNPP

Floating nuclear power plant (FNPP) is a nuclear reactor emplaced and operated above water surface and has mobile ability. This reactor design enables nuclear reactor facility mobilization from the electrical grid location at the seashore or mobilized towards the shipyard for maintenance of the ship and the reactor away from electrical generation site. Other characteristics of this SMR design is its small volumetric size and low generated power. This reactor can be used for cogeneration such as desalinating seawater. Another cogeneration application is the district heating function such as room heating.

List of relevant theses:

  1. Subchannel Analysis on KLT-40S Fuel Assembly to Determine the Minimum Departure from Nucleate Boiling (MDNBR) using SUBCHANFLOW, I Putu Krisna Kuumbara, 2022.
  2. Study on Neutronic Parameters of the KLT-40S Reactor Core with Accident Tolerant Fuels (ATF) U3Si2-FeCrAl using SCALE, Alif Al Mahfudz, 2022
  3. Subchannel Analysis on KLT-40S Reactor Fuel Assembly to Calculate the Distribution of Hydraulic Thermal Characteristics using RELAP5-3D, Agung Krisna Mukti, 2022.
  4. Thermal Hydraulics Study on the Primary Loop of KLT-40S during RCP Coastdown, M. Faris Alkodri, 2020.
  5. Point Dynamics Simulation of KLT-40s Floating Nuclear Power Plant in Rolling-Heaving and Pitching-Heaving Motion at Various Sea State Condition, I Gusti Bagus Awienandra, 2019.
  6. Coupled Neutronics-Thermalhydraulics for Steady and Transient Pressure and Inlet Mass Flow Rate in KLT-40s Reactor using RELAP5-3D, Ade Chandra Lesmana, 2019.
  7. Analysis of Motion Effect on KLT-40S Reactor Pressure Vessel in a Floating Craft due to Ocean Wave upon Thermal Hydraulics Characteristics of Reactor using RELAP5-3D, Tommy Suhartanto Wijaya Tan, 2018.
  8. Modeling and Analysis of Thermal Hydraulics Operation Parameters of KLT-40s Reactor At Steady And Transient Condition Using Relap5-3D, Abednego Kristanto, 2017.
  9. The Study of KLT-40s Floating Nuclear Power Plant Reactor Core Neutronic Parameter Using SCALE 6.1 Simulation Code,Dhirar Faisal Fajri, 2017.
  10. Design Analysis of Fuel Assembly and Reactor Core of Floating Nuclear Power Plant KLT-40s using SERPENT Code, Kevin Ahimsa, 2017.
  11. A Study on The Effects of Primary Thermohydraulic System Parameter Change on The Power and Void Fraction Generated in The Helical Coil Steam Generator for KLT-40s Reactor, Sardini Sayyidatun Nisa, 2017.

Tawaran Tugas Akhir

  • Aspek Termal Hidraulika
    • Refining model teras
    • Refining model steam generator
    • Pemodelan helical coil SG menggunakan CFD
    • Simulasi event atau kejadian
      • LOCA
      • MSLB
      • LOFA with reactivity feedback
      • CR ejection
    • Penentuan uncertainty band
    • Analisis sub kanal
  • Aspek Neutronika
    • Pemodelan teras reaktor KLT-40S berbahan bakar alternatif (mixed U-Th, UN, ATF)
    • Desain ulang fuel assembly dan teras
      • In-core fuel management
      • Penggunaan burnable poison
  • Penyimpanan fresh dan spent fuel
    • Criticality safety
    • Desain perisai radiasi
  • Kopling neutronika, termal hidraulika dan gerakan kapal