JOPSS - Search Results

JAEA Reports

Microstructural observation of simulated fuel kernels for Pu-burner high temperature gas-cooled reactor in Japan

Aihara, Jun; Ueta, Shohei; Honda, Masaki*; Kasahara, Seiji; Okamoto, Koji*

JAEA-Research 2024-012, 98 Pages, 2025/02

JAEA-Research-2024-012.pdf:32.24MB

Concept of Pu-burner high temperature gas-cooled reactor (HTGR) was proposed for the purpose of more safely reducing amount of recovered Pu. In Pu-burner HTGR concept, coated fuel particle (CFP), with ZrC coated yttria stabilized zirconia (YSZ) containing PuO $_{2}$ (PuO $_{2}$ -YSZ) small particle and with tri-structural isotropic (TRISO) coating, is employed for very high burn-up and high nuclear proliferation resistance. ZrC layer is oxygen getter. In research project of Pu-burner HTGR carried out from fiscal year of 2014 to fiscal year of 2017, simulated CFPs were fabricated using Ce to simulate Pu. Moreover, simulated fuel compacts were fabricated using fabricated simulated CFPs. In this report, results of microstructural observation of CeO $_{2}$ -YSZ and ZrC layer at each fabrication step are reported.

JAEA Reports

Code-B-2.5.2 for stress calculation for SiC-TRISO fuel particle

Aihara, Jun; Goto, Minoru; Ueta, Shohei; Tachibana, Yukio

JAEA-Data/Code 2019-018, 22 Pages, 2020/01

JAEA-Data-Code-2019-018.pdf:1.39MB

Concept of Pu-burner high temperature gas-cooled reactor (HTGR) was proposed for purpose of more safely reducing amount of recovered Pu. In Pu-burner HTGR concept, coated fuel particle (CFP), with ZrC coated yttria stabilized zirconia (YSZ) containing PuO $_{2}$ (PuO $_{2}$ -YSZ) small particle and with tri-structural isotropic (TRISO) coating, is employed for very high burn-up and high nuclear proliferation resistance. ZrC layer is oxygen getter. On the other hand, we have developed Code-B-2.5.2 for prediction of pressure vessel failure probabilities of SiC-tri-isotropic (TRISO) coated fuel particles for HTGRs under operation by modification of an existing code, Code-B-2. The main purpose of modification is preparation of applying code for CFPs of Pu-burner HTGR. In this report, basic formulae are described.

Journal Articles

Defect chemistry and basic properties of non-stoichiometric PuO $_{2}$

Kato, Masato; Nakamura, Hiroki; Watanabe, Masashi; Matsumoto, Taku; Machida, Masahiko

Defect and Diffusion Forum, 375, p.57 - 70, 2017/05

http://doi.org/10.4028/www.scientific.net/DDF.375.57

The basic properties of PuO $_{2-x}$ were reviewed, and the equilibrium defects in PuO $_{2-x}$ were evaluated from the experimental data of the oxygen potential and electrical conductivity as well as the Ab-initio calculation results. Consistency among various properties was confirmed, and the mechanistic models for thermal property representations were derived.

Journal Articles

Sintering behavior of (U,Ce)O $_{2}$ and (U,Pu)O $_{2}$

Nakamichi, Shinya; Hirooka, Shun; Sunaoshi, Takeo*; Kato, Masato; Nelson, A.*; McClellan, K.*

Transactions of the American Nuclear Society, 113(1), p.617 - 618, 2015/10

Cerium dioxide has been used as a surrogate material for plutonium dioxide. Dorr et al reported the use of hyper-stoichiometric conditions causes the start of shrinkage of (U,Ce)O $_{2}$ at low temperature compared with the sintering in reducing atmosphere. However, the precise stoichiometry of the samples investigated was not controlled or otherwise monitored, preventing any quantitative conclusions regarding the similarities or differences between (U,Ce)O $_{2}$ and (U,Pu)O $_{2}$ . The motivation for the present work is therefore to compare the sintering behavior of MOX and the (U,Ce)O $_{2}$ MOX surrogates under controlled atmospheres to assess the role of oxygen defects on densification in both systems.

Journal Articles

Chlorination of UO $_{2}$ , PuO $_{2}$ and rare earth oxides using ZrCl $_{4}$ in LiCl-KCl eutectic melt

Sakamura, Yoshiharu*; Inoue, Tadashi*; Iwai, Takashi; Moriyama, Hirotake*

Journal of Nuclear Materials, 340(1), p.39 - 51, 2005/04

https://doi.org/10.1016/j.jnucmat.2004.11.002

Times Cited Count：47 Percentile：92.96(Materials Science, Multidisciplinary)

A new chlorination method using ZrCl $_{4}$ in a molten salt has been investigated for the pyrometallurgical reprocessing of spent oxide fuels. UO $_{2}$ , PuO $_{2}$ and rare earth oxides(La $_{2}$ O $_{3}$ , CeO $_{2}$ , Nd $_{2}$ O $_{3}$ and Y $_{2}$ O $_{3}$ ) were allowed to react with ZrCl $_{4}$ in a LiCl-KCl eutectic salt at 500 $^{circ}$ C to give a metal chloride solution and a precipitate of ZrO $_{2}$ . By keeping the system quite still, the solution settled so that the ZrO $_{2}$ precipitate could be separated.

Journal Articles

Studies in the PuO $_{2}$ -ZrO $_{2}$ pseudo-binary phase diagram

Albiol, T.*; Serizawa, Hiroyuki; Arai, Yasuo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.834 - 837, 2002/11

http://www.tandfonline.com/doi/abs/10.1080/00223131.2002.10875598

no abstracts in English

Journal Articles

Re-evaluation of the phase relationship between plutonium and zirconium dioxides

Serizawa, Hiroyuki; Nakajima, Kunihisa; Arai, Yasuo; Yamashita, Toshiyuki; Kuramoto, Kenichi; Kinoshita, H.*; Yamanaka, Shinsuke*; Uno, Masayoshi*; Kurosaki, K.*

Progress in Nuclear Energy, 38(3-4), p.237 - 240, 2001/02

https://doi.org/10.1016/S0149-1970(00)00107-4

Times Cited Count：5 Percentile：38.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles