Development of an integrated active neutron non-destructive analysis system; Active-N

Toh, Yosuke; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo

Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 8 Pages, 2021/08

Development of active neutron NDA system

Toh, Yosuke

JAEA-Conf 2019-001, p.47 - 52, 2019/11

https://doi.org/10.11484/jaea-conf-2019-001

no abstracts in English

Development of active neutron NDA system for nuclear materials

Toh, Yosuke; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo; Heyse, J.*; Paradela, C.*; et al.

Proceedings of INMM 59th Annual Meeting (Internet), 9 Pages, 2018/07

Development and implementation of GloveBox Cleanout Assistance Tool (BCAT) to detect the presence of MOX by computational approach

Nakamura, Hironobu; Nakamichi, Hideo; Mukai, Yasunobu; Hosoma, Takashi; Kurita, Tsutomu; LaFleur, A. M.*

Proceedings of International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (M&C 2017) (USB Flash Drive), 7 Pages, 2017/04

In order to maintain facility nuclear material accountancy (NMA) and safeguards properly, to understand where and how much holdup deposit in the process is presence is very important for the cleanout before PIT. JAEA and LANL developed a GloveBox Cleanout Assistance Tool (BCAT) to help cleanout (MOX powder recovering in a glovebox) for invisible holdup effectively by computational approach which is called distributed source-term approach (DSTA). The BCAT tool is a simple neutron measurement slab detectors and helps operator to find locations of holdup. To know the holdup location and the activity from the neutron measurements, the relation between BCAT measurements results at predetermined positions (57 positions) and source voxels (53 voxels) that we want to know the holdup activity was mathematically defined as a matrix by the MCNPX simulation. The model of MCNPX for entire process is very precisely established. We have implemented and experimentally proved that the BCAT tool can direct the operator to recoverable holdup that would otherwise be accounted for as MUF. Reducing facility MUF results in a direct improvement of the facility NMA. The BCAT enables the staff to significantly improve their knowledge of the locations of residual holdup in the process area. JAEA would like to use this application for dismantling of the glovebox with transparency in the future.

Design study on differential die-away technique in an integrated active neutron NDA system for non-nuclear proliferation

Ozu, Akira; Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Kureta, Masatoshi; Koizumi, Mitsuo; Seya, Michio

Proceedings of 2016 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2016) (Internet), 4 Pages, 2016/00

http://doi.org/10.1109/NSSMIC.2016.8069710

no abstracts in English

Non-Destructive Measurement System of Water Velocity in an Unsaturated Porous Medium Using Micro-Computer

; Yamamoto, Tadatoshi

JAERI-M 85-096, 21 Pages, 1985/07

JAERI-M-85-096.pdf:0.77MB

no abstracts in English

Characterization study of candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station, 2; Passive neutron technique (Interim report)

Nomi, Takayoshi; Nagatani, Taketeru; Shiromo, Hideo; Asano, Takashi

no journal, , 

This report describes applicability evaluation results of the passive neutron technique (PN) for characterization study of candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station. The PN consists of Differential Die-away Self-Interrogation (DDSI) and neutron coincidence counting. The DDSI evaluates the neutron multiplication and absorption effect and corrected coincidence count rate determines Cm-244 effective mass. Nuclear material is quantified by using isotopic composition from code calculation or ray measurement. The simulation results indicate that the PN is applicable to B-10 contained fuel debris. The results also indicate that the major uncertainty factor is the variation of water content. To minimize it, classification of rough water fill ratio in a canister such as wet storage or dry storage will be required.

Characterization study of four candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station, 2; Numerical simulations for passive neutron technique

Nomi, Takayoshi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Shiromo, Hideo; Asano, Takashi

no journal, , 

Development of active neutron NDA apparatus for nuclear non-proliferation and nuclear security, 1; Project overview and development of Prompt Gamma-ray Analysis system

Toh, Yosuke; Furutaka, Kazuyoshi; Ozu, Akira; Tsuchiya, Harufumi; Kitatani, Fumito; Maeda, Makoto; Komeda, Masao; Koizumi, Mitsuo; Seya, Michio

no journal, , 

no abstracts in English

Needs for neutron source and nuclear data in developments of an active neutron non-destructive system

Toh, Yosuke; Maeda, Makoto; Tsuchiya, Harufumi; Ozu, Akira; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao

no journal, , 

no abstracts in English