Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor

Abstract

The pebble bed type High Temperature Gas-cooled Reactor (HTGR) is among the interesting nuclear reactor designs in terms of safety and flexibility for cogeneration applications. In addition, the strong inherent safety characteristics of the pebble bed reactor (PBR) which is based on natural mechanisms improve the simplicity of the PBR design, in particular for the Once-Through-Then-Out (OTTO) cycle PBR design. One of the important challenges of the OTTO cycle PBR design, and nuclear reactor design in general, is improving the nuclear fuel utilization which is shown by attaining a higher burnup value. This study performed a preliminary neutronic design study of a 200 MWt OTTO cycle PBR with high burnup while fulfilling the safety criteria of the PBR design.The safety criteria of the design was represented by the per-fuel-pebble maximum power generation of 4.5 kW/pebble. The maximum burnup value was also limited by the tested maximum burnup value which maintained the integrity of the pebble fuel. Parametric surveys were performed to obtain the optimized parameters used in this study, which are the fuel enrichment, per-pebble heavy metal (HM) loading, and the average axial speed of the fuel. An optimum design with burnup value of 131.1 MWd/Kg-HM was achieved in this study which is much higher compare to the burnup of the reference design HTR-MODUL and a previously proposed OTTO-cycle PBR design. This optimum design uses 17% U-235 enrichment with 4 g HM-loading per fuel pebble.

Preliminary Analysis of Core Temperature Distribution of Experimental Power Reactor Using Relap5

“…These factor will be used in defining the power factor distribution of the pebbles, which generate heat in the core, as the heat structure components in the RELAP5. For that purpose, data from the EPR basic design document are used representing the power distribution in the OTTO (once through then out) refueling scheme, in which each pebble only passes the core once [12]. Figure 2 shows the scheme of the RELAP5 nodalization in the core zones, fuel discharge tube, outlet channels, and the hot gas plenum.…”

Pengaruh Perisai Radiasi Pada Penyimpanan Kering Bahan Bakar Nuklir Bekas untuk Reaktor Daya Eksperimental

“…HTR-10 dipilih karena memiliki tingkat keselamatan yang cukup baik dan menghasilkan energi yang besar sehingga dapat dimanfaatkan untuk proses kogenerasi. Selain itu, reaktor ini nantinya akan dikembangkan untuk memenuhi kebutuhan listrik di Indonesia [2], [7].…”

Analisis Inventori Reaktor Daya Eksperimental Jenis Reaktor Gas Temperatur Tinggi

“…Beberapa peneliti telah melakukan penelitian untuk reaktor HTGR, antara lain tentang teras reaktor HTGR merujuk pada pustaka [10,11,12,13,14,15,16] , juga pene-litian tentang bahan bakar TRISO oleh peneliti sesuai pustaka [17,18,19] . Penelitian lain juga melakukan penelitian tentang keselamatan reaktor HTGR yaitu Zuhair dan kawan-kawan mengenai efek kecelakaan water ingress pada reaktor HTGR sesuai pustaka [20] .…”