Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme
This research investigates the impact of changes in reactor geometry to discover more
optimal dimensional options for nuclear power plants with potential applications in remote …
optimal dimensional options for nuclear power plants with potential applications in remote …
Analysis of TRISO failure fraction in PeLUIt reactor with increasing power
This study investigates the impact of increasing power in the PeLUIt reactor on the failure
fraction of TRISO-coated fuel particles during both normal operation and Depressurized …
fraction of TRISO-coated fuel particles during both normal operation and Depressurized …
Implementation of thorium-based fuel for Indonesia Micro Reactor (IMR)
Indonesia has committed to reducing greenhouse gas emissions in the framework of net
zero emissions, and nuclear energy will be a part of the energy mix. Indonesia has been …
zero emissions, and nuclear energy will be a part of the energy mix. Indonesia has been …
Computational analysis for predicting fission product release of PeLUIt-40 under normal operating conditions
Abstract PeLUIt (Pembangkit Listrik dan Uap untuk Industri) is an High Temperature Gas
Cooled Reactor (HTGR)-based cogeneration reactor designed by the Indonesian National …
Cooled Reactor (HTGR)-based cogeneration reactor designed by the Indonesian National …
Scaling law method for cost estimation of Indonesia's first HTGR (PeLUIt-40) and its implementation strategy
The Indonesian government has planned to build its first high-temperature gas reactor
(HTGR), PeLUIt-40. A lack of estimates for PeLUIt-40′ s costs hamper planning and …
(HTGR), PeLUIt-40. A lack of estimates for PeLUIt-40′ s costs hamper planning and …
[HTML][HTML] Heavy metal loading effects on special nuclear material and waste of an uprated Indonesian Reaktor Daya Eksperimental
This technical policy study investigated the effect of heavy metal loading (HML) quantity in
the pebble fuel on the special nuclear material (SNM) and waste quantities of an uprated …
the pebble fuel on the special nuclear material (SNM) and waste quantities of an uprated …
[PDF][PDF] THERMAL HYDRAULIC SAFETY CONSIDERATIONS, METHODS AND RESEARCH FOR HIGH-TEMPREATURE GAS-COOLED REACTORS (HTGRs)
X Huang, S He - Proceedings of the 18th UK Heat Transfer …, 2024 - more.bham.ac.uk
1. ABSTRACT A literature review is conducted on the approaches that High Temperature
Gas-Cooled Reactor (HTGR) vendors, designers and R&D engineers have used to justify …
Gas-Cooled Reactor (HTGR) vendors, designers and R&D engineers have used to justify …