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Ho, H. Q.; 本多 友貴; 後藤 実; 高田 昌二
Annals of Nuclear Energy, 112, p.42 - 47, 2018/02
被引用回数：8 パーセンタイル：62.99(Nuclear Science & Technology)Coated fuel particle (CFP) is one of important factors attributing to the inherent safety feature of high temperature engineering test reactor (HTTR). However, the random arrangement of CFPs makes the simulation more complicated, becoming one of the factors affects the accuracy of the HTTR criticality calculations. In this study, an explicit random model for CFPs arrangement, namely realized random packing (RRP), was developed for the whole core of HTTR using a Monte-Carlo MCNP6 code. The effect of random placement of CFPs was investigated by making a comparison between the RRP and conventional uniform models. The results showed that the RRP model gave a lower excess reactivity than that of the uniform model, and the more number of fuel columns loading into the core, the greater the difference in excess reactivity between the RRP and uniform models. For example, the difference in excess reactivity increased from 0.07 to 0.17%
k/k when the number of fuel column increased from 9 to 30. Regarding the control rods position prediction, the RRP showed the results, which were closer to experiment than the uniform model. In addition, the difference in control rods position between the RRP and uniform models also increases from 12 to 17 mm as increasing number of fuel columns from 19 to 30.
Ho, H. Q.; 守田 圭介*; 本多 友貴; 藤本 望*; 高田 昌二
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04
The Coated Fuel Particle plays an important role in the excellent safety feature of the High Temperature Gas-cooled Reactor. However, the random distribution of CFPs also makes the simulation of HTGR fuel become more complicated. The Monte Carlo N-particle (MCNP) code is one of the most well-known codes for validation of nuclear systems; unfortunately, it does not provide an appropriate function to model a statistical geometry explicitly. In order to deal with the stochastic media, a utility program for the random model, namely Realized Random Packing (RRP), has been developed particularly for High Temperature engineering Test Reactor (HTTR). This utility program creates a number of random points in an annular geometry. Then, these random points will be used as the center coordinate of CFPs in the MCNP6 input file and therefore the actual random arrangement of CFPs can be simulated explicitly. First, a pin-cell calculation was carried out to validate the RRP by comparing with Statistical Geometry (STG) model of MVP code. After that, the comparison between the RRP model (MCNP) and STG model (MVP) was shown in whole core criticality calculation, not only for the annular core but also for the fully-loaded core. The comparison of numerical results showed that the RRP model and STG model differed insignificantly in the multiplication factor as expected, regardless of the pin-cell or whole core calculations. In addition, the RRP model did not make the calculation time increase a lot in comparison with the conventional regular model (uniform arrangement).
Ho, H. Q.; 本多 友貴; 後藤 実; 高田 昌二
no journal, ,
This study investigated several stochastic geometry treatments for the coated fuel particles (CFPs) in the high temperature engineering test reactor (HTTR) fuel compact. The criticality calculations were carried out by using MCNP5 for a single fuel block with reflecting boundary condition. The infinite multiplication factor (kinf) of these random arrangements was about 0.03% - 0.15% difference compared to that of regular (uniform) arrangement. The random packing CFPs in an annular lattice showed the highest kinf due to non-truncated CFPs in this model.
Ho, H. Q.; 本多 友貴; 後藤 実; 高田 昌二; 石塚 悦男
no journal, ,
被覆燃料粒子(CFP)は、高温工学試験研究炉(HTTR)の受動的安全機能に重要な役割を果たす。しかし、CFPのランダムな分布は、シミュレーションを困難にし、HTGRのベンチマーク評価に影響を与える。高精度な計算は、HTGRの低コスト化と高性能化につながる。本研究の目的は、ベンチマーク評価の精度を向上させるために、より正確なランダムモデル、すなわち現実的なランダムパッキング(RRP)を用いてHTTRのMCNPモデルを開発することである。RRPモデルは、従来の均一モデルおよび実験データと比較することによって検証された。中性子及び臨界計算は、ENDF/B-VII.1核データライブラリーを用いたMCNP6コードを用いて行った。
Ho, H. Q.; 本多 友貴; 後藤 実; 高田 昌二; 石塚 悦男
no journal, ,
The Monte-Carlo MCNP code does not provide an appropriate model to simulate random arrangement of coated fuel particles (CFPs) in the fuel compact of high temperature engineering test reactor (HTTR). This study developed a MCNP model for the HTTR by using an explicit random method, namely realized random packing (RRP), to improve the accuracy of the benchmark assessment. Criticality results showed that by using the RRP model the accuracy of HTTR benchmark could be improved in comparison with the conventional uniform model.
