Preventing nuclear fuel material adhesion on glove box components using nanoparticle coating

Segawa, Tomoomi; Kawaguchi, Koichi; Ishii, Katsunori; Suzuki, Masahiro; Tachihara, Joji; Takato, Kiyoto; Okita, Takatoshi; Satone, Hiroshi*; Suzuki, Michitaka*

Mechanical Engineering Journal (Internet), 8(3), p.21-00022_1 - 21-00022_9, 2021/06

https://doi.org/10.1299/mej.21-00022

To reduce the hold-up of the nuclear fuel materials in the glove box and the external exposure dose, the technology of the MOX powder adhesion prevention by the nanoparticle coating to the acrylic panels of the glove box has been developed. The surface analysis by means of atomic force microscopy (AFM) showed that the acrylic test piece surface coated with nanoparticles had a higher root mean square roughness value than that non-coated with nanoparticles. Due to the formation of nano-sized tiny rugged surface, the nanoparticle coating reduced the minimum adhesion force between the UO particles and the acrylic test piece surface with the smallest particle size of about 5 m where desorption was observed, by about one-tenth. Moreover, the nanoparticle coating reduced the amount of the MOX powder adhering to the acrylic test piece to about one-tenth. In this study, it was found that applying the nanoparticle coating to the acrylic panels of glove box can prevent the adhesion of nuclear fuel materials. This method is effective for reducing the hold-up of the nuclear fuel materials in the glove box, the external exposure dose and improving the visibility of the acrylic panels.

Damage evaluation techniques for FBR and LWR structural materials based on magnetic and corrosion properties along grain boundaries

Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*

Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06

JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.

Evaluation of corrosion behavior of ion irradiated stainless steel using atomic force microscope

Nemoto, Yoshiyuki; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi

Nihon AEM Gakkai-Shi, 11(4), p.242 - 248, 2003/12

no abstracts in English

Influence of H and He on corrosion behavior of ion irradiated stainless steel

Nemoto, Yoshiyuki; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi; Abe, Hiroaki*; Sekimura, Naoto*

JAERI-Review 2003-033, TIARA Annual Report 2002, p.171 - 173, 2003/11

https://jopss.jaea.go.jp/pdfdata/JAERI-Review-2003-033-p0001-p0187.pdf

The aim of this work is to evaluate corrosion behavior of irradiated materials for mechanistic understanding of irradiation assisted stress corrosion cracking (IASCC). Solution annealed high purity Fe-18Cr-12Ni specimens were used in this study. H and He were implanted during irradiation with 12MeV Ni ion at 573K. After corrosion procedure, the specimens were examined with atomic force microscope (AFM) to evaluate corrosion behavior. It was shown that the corroded volume of irradiated area increased with radiation damage. H implantation at lower temperature accelerated corrosion. He implantation suppressed corrosion.

AFM evaluation for corrosion behavior of ion irradiated stainless steel

Nemoto, Yoshiyuki; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 7 Pages, 2003/04

Irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steel has been studied as main concern of an aging problem of light water reactor (LWR) materials. It is essential to evaluate corrosion behavior of irradiated materials for mechanistic understanding of IASCC. The aim of this work is to evaluate the corrosion behavior of ion irradiated materials using atomic force microscope (AFM), and evaluate the influence of radiation temperature, radiation damage, H and He implantation.

AFM observation of nanosized SiC dots prepared by ion beam deposition

Xu, Y.; Narumi, Kazumasa; Miyashita, Kiyoshi*; Naramoto, Hiroshi

Surface and Interface Analysis, 35(1), p.99 - 103, 2003/01

https://doi.org/10.1002/sia.1502

no abstracts in English

Morphology evolution of thin Ni film on MgO(100) substrate

Lin, C.; Xu, Y. H.; Naramoto, Hiroshi; Wei, P.; Kitazawa, Shinichi; Narumi, Kazumasa

Journal of Physics D; Applied Physics, 35(15), p.1864 - 1866, 2002/08

https://doi.org/10.1088/0022-3727/35/15/308

no abstracts in English

Design and manufacture of apparatus for analysis of atomic process on solid surfaces

Teraoka, Yuden; Yoshigoe, Akitaka

JAERI-Tech 2001-009, 41 Pages, 2001/03

JAERI-Tech-2001-009.pdf:1.99MB

no abstracts in English

Study on ferroelectric domains in BaTiO crystalline films and bulk crystals by atomic force and scanning electron microscopies

Tsunekawa, Shin*; Fukuda, Tsuguo*; Ozaki, Toru*; Yoneda, Yasuhiro; Okabe, Toru*; Terauchi, Hikaru*

Journal of Applied Physics, 84(2), p.999 - 1002, 1998/06

https://doi.org/10.1063/1.368167

no abstracts in English

Irradiation test of HAFM and tag gas samples at the standard neutron field of "YAYOI"

PNC TJ9602 96-004, 49 Pages, 1996/03

PNC-TJ9602-96-004.pdf:1.53MB

To check the accuracy of helium accumulation neutron fluence monitoring (HAFM) technique and the applicability of tag gas activation analysis to fast reactor failed fuel detection, these samples were irradiated at the standard neutron field of the fast neutron source reactor "YAYOI" (Nuclear Engineering Research Laboratory, University of Tokyo). The HAFM samples of 93% enriched B powder of 1 mg contained in a V capsule were set up in the reactor core center (Glory hole :Gy) and another samples including V encapsulated natural B powder of 10 mg, natural B chips and 96% enriched LiF thermoluminescence dosimeters were in the leakage neutron field from the reactor core (Fast column :FC). These neutron fields were monitored by the activation foils consisting of Al, Fe, Co, Ni, Cu, Ti, In, Au, U, Np etc., which were used to derive the neutron flux and spectrum. At the end of March in 1996, the irradiated neutron fluence in the energy more than 0.1Mev reached up to 1.110 n/cm at Gy and 5.410 n/cm at FC, respectively. Two kinds of tag gas samples, which are the mixed gases of isotipically adjusted Xe and Kr contained in stainless steel (SUS) capsules, were irradiated twice at Gy; one is up to 9kWh and the other 7kWh, and after the irradiation, -ray spectra were measured for each sample. Through comparison with the -ray spectrum from dummy capsule of no tag gas, the -ray peaks of Kr, Xe etc., which would be produced from tag gas activation, were able to be clearly identified.