Synthesis and characterization of CeO-based simulated fuel containing CsI

Takamatsu, Yuki*; Ishii, Hiroto*; Oishi, Yuji*; Muta, Hiroaki*; Yamanaka, Shinsuke*; Suzuki, Eriko; Nakajima, Kunihisa; Miwa, Shuhei; Osaka, Masahiko; Kurosaki, Ken*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 17(3/4), p.106 - 110, 2018/12

https://doi.org/10.3327/taesj.J17.025

In order to establish the synthesis method of simulated fuel contacting Cesium (Cs) which is required for the evaluation of physical/chemical characteristics in fuel and release behavior of Cs, sintering tests of the cerium dioxide (CeO) based simulated fuels containing Cesium iodide (CsI) are performed by using spark plasma sintering (SPS) method. The sintered CeO pellets with homogeneous distribution of several micro meter of CsI spherical precipitates were successfully obtained by optimizing SPS conditions.

Preparation of microvolume anion-exchange cartridge for inductively coupled plasma mass spectrometry-based determination of Np content in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

Analytical Chemistry, 88(6), p.3149 - 3155, 2016/03

https://doi.org/10.1021/acs.analchem.5b04330

Neptunium-237 (Np) is one of the major long-lived radionuclides found in spent nuclear fuel. To evaluate the long-term safety of a HLW repository, the Np content in spent nuclear fuel must be determined. In this study, micro-volume anion-exchange porous polymer disk-packed cartridges were prepared for Am-Np separation, which is required prior to the measurement of Np with ICP-MS. Disks with a volume of 0.08 cm were cut out from porous sheets having triethylenediamine (TEDA)-containing polymer chains densely attached on the pore surface. The resulting TEDA-introduced disk cartridge was applied to a spent nuclear fuel sample. The chemical yield of Np was 90.4%, which is sufficiently high for ICP-MS measurement of Np. Compared with the conventional separation technique using commercially available anion-exchange resin columns, the time required to adsorb, wash and elute Np using the TEDA-introduced disk cartridge was reduced by 75%.

MeV -ray generation from backward Compton scattering at SPring-8

Kawase, Keigo; Arimoto, Yasushi*; Fujiwara, Mamoru; Okajima, Shigeki*; Shoji, Masazumi*; Suzuki, Shinsuke*; Tamura, Kazuhiro*; Yorita, Tetsuhiko*; Okuma, Haruo*

Nuclear Instruments and Methods in Physics Research A, 592(3), p.154 - 161, 2008/07

https://doi.org/10.1016/j.nima.2008.04.008

A test experimental line at SPring-8 has been constructed for the generation of backward Compton scattered (BCS) -ray by head-on collision between an 8 GeV electron beam and a far-infrared (FIR) laser. For the FIR laser, we use a continuous-wave methanol laser optically pumped by a carbon dioxide () laser. The FIR laser output power achieved is 1.6 W at maximum for 118.8 m lasing; this value is the highest in the case of this type of laser. As a result of the direct measurement, the generated BCS -ray flux was found to be about photons/s. This value is consistent with the estimation calculated by taking into account the input laser power and the transmittance of the laser transport system.

General expression for current transformer

; Yoshikawa, Hiroshi; ; ; Hori, Toshihiko*; Ito, Yuichi*; Yokomizo, Hideaki

Japanese Journal of Applied Physics, 35(10), p.5530 - 5538, 1996/10

https://doi.org/10.1143/JJAP.35.5530

no abstracts in English

Wall current monitor for SPring-8 linac

; *; *; ; *; Yoshikawa, Hiroshi; ; Sakaki, Hironao; *; Yokomizo, Hideaki

JAERI-M 94-078, 29 Pages, 1994/06

JAERI-M-94-078.pdf:1.05MB

no abstracts in English

Simulation of electron-positron convertor for SPring-8

; ; Yoshikawa, Hiroshi; *; ; Yokomizo, Hideaki

JAERI-M 93-030, 40 Pages, 1993/03

JAERI-M-93-030.pdf:1.07MB

no abstracts in English

Development of beam diagnostics for SPring-8 linac

; ; Ito, Yuichi*; Yoshikawa, Hiroshi; ; *; Yokomizo, Hideaki

AECL-10728 (Vol. 2), p.665 - 667, 1992/00

no abstracts in English

Axial magnetic focusing field on bunching section

Yoshikawa, Hiroshi; Nakamura, Naoki*; ; ; ; *; ; Yokomizo, Hideaki

Proc. of the 17th Linear Accelerator Meeting in Japan, p.144 - 146, 1992/00

no abstracts in English

Anion-exchange porous polymer sheet for rapid analysis of Np in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

no journal, , 

no abstracts in English

Performance evaluation of micro-volume anion-exchange filter prepared by graft polymerization on Zr separation and its application to determination of Zr-93 in spent fuel

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

no journal, , 

Zr is a long-lived fission product which can be found in spent nuclear fuel and HLW. The estimation of theZr content is indispensable to achieve a safety disposal of HLW because Zr is predicted to be one of the major contributors to radiation dose. However, only a few measured Zr values have been reported, leading to a high demand for development of an efficient analytical method. Our group has been prepared a new porous filter cartridge which has densely bound ion-exchanger onto the pore surface of the filter, enabling a high-capacity and rapid adsorption. In order to apply this filter cartridge to a pretreatment for the Zr measurement with ICP-MS, an elution profiles of Zr and the other coexisting elements were examined. According to the resultant separation conditions, Zr in a spent nuclear fuel sample was successfully separated. The measured Zr content is 98.2 5.1 ng, which agrees with the theoretical value.