Conceptual design study of a high performance commercial HTGR for early introduction

Fukaya, Y.; Mizuta, Naoki; Goto, Minoru; Ohashi, Hirofumi; Yan, Xing

doi:10.1016/j.nucengdes.2020.110577

Cited by 4 publications

(1 citation statement)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Research and development of HTGR are currently under rapid progress, especially in several countries like China, as reported by Dongqinga et al, 6 Lin et al, 7 Zhang et al, 8 and Japan, as reported by Fukaya et al, 9 Sato et al, 10 Ueta et al 11 Furthermore, Indonesia, as reported by T. Setiadipura et al 12 Each of these countries develops its specific design based on the purpose of the development.…”

Section: Introductionmentioning

confidence: 99%

Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor

Irwanto

Pratama

2021

Intl J of Energy Research

View full text Add to dashboard Cite

Summary High‐temperature gas reactor (HTGR) is one of the Generation IV nuclear reactors currently undergoing rapid development in the world. The utilization of fissile material becomes an important parameter in HTGR technology because of the use of layered particle‐type fuel that makes it challenging to reprocess. This research aims to compare and optimize the fissile utilization of HTGR 60 MWt using UO2, (Th‐U)O2, and (Pu‐U)O2. The utilization of fissile material on HTGR is being studied in this research by using the SRAC (Standard Reactor Analysis Code) version 2006 and the Japanese Evaluated Nuclear Data Library (JENDL) version 4.0. Parametric surveys are performed for important neutronic parameters, including analyzing the effects of fuel enrichment and the coated fuel particle (CFP) amount. Fissile materials are analyzed on a 1% to 20% enrichment level, and the CFP number is varied from 4470 to 26 830. The neutronic parameters taken into account are k‐inf, conversion ratio (CR), the density of fissile and fertile material, and neutron energy spectrum. The results suggest that 11% of fuel enrichment and CFP number between 8950 and 11 180 are optimal for 60MWt HTGR. The highest fuel utilization level at the end of the reactor period was achieved by Pu‐based fuel, with 81.6% of utilized fissile material.

show abstract