Comparing DGSMC, FIER, and FISPACT simulations to experimental delayed gamma-ray spectra for nuclear safeguards development

Rodriguez, D.; Rossi, F.; Takahashi, Tone

IEEE Transactions on Nuclear Science, 71(3), p.255 - 268, 2024/03

https://doi.org/10.1109/TNS.2024.3353816

Efforts for appropriate responses to safeguards activities, 1; Overview

Aoki, Rie; Shirafuji, Masaya; Nozaki, Teo; Akutsu, Narumi*; Miyaji, Noriko; Nakamura, Hironobu

Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 7 Pages, 2023/05

Design and characterization of the fission signature assay instrument for nuclear safeguards

Rossi, F.; Koizumi, Mitsuo; Rodriguez, D.; Takahashi, Tone

Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 5 Pages, 2023/05

New design of a delayed gamma-ray spectrometer for safeguards verification of small mixed nuclear material samples

Rossi, F.; Koizumi, Mitsuo; Rodriguez, D.; Takahashi, Tone

Proceedings of 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference (2022 IEEE NSS MIC RTSD) (Internet), 2 Pages, 2022/11

Developing delayed gamma-ray spectroscopy for nuclear safeguards; Project overview and analysis development

Rodriguez, D.; Abbas, K.*; Koizumi, Mitsuo; Nonneman, S.*; Oberstedt, S.*; Pedersen, B.*; Rossi, F.; Schillebeeckx, P.*; Takahashi, Tone

Proceedings of INMM 63rd Annual Meeting (Internet), 9 Pages, 2022/09

Study of rational safeguards for the treatment of radioactive waste containing nuclear materials

Nakatani, Takayoshi; Shimizu, Ryo; Tazaki, Makiko; Kimura, Takashi; Tamai, Hiroshi; Suda, Kazunori

Dai-42-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2021/11

Currently, JAEA is in the advancing of decommissioning own nuclear facilities, and some facilities have been handling nuclear materials. In decommissioning, it is necessary to consider rational methods while keeping nuclear non-proliferation and transparency, including treatment of radioactive waste generated from these facilities and methods for terminating safeguards. In this study, we considered the above issues regarding waste treatment with reference to the guidance of Safeguards by Design (SBD) published by the International Atomic Energy Agency (IAEA).

Development of delayed gamma-ray spectroscopy for nuclear safeguards, 2; Designing a compact DGS instrument

Rossi, F.; Abbas, K.*; Koizumi, Mitsuo; Lee, H.-J.; Rodriguez, D.; Takahashi, Tone

Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 7 Pages, 2021/08

JAEA-JRC collaborative development of delayed gamma-ray spectroscopy for nuclear material evaluation, 3; Fissile mass estimation with uranium samples

Rossi, F.; Koizumi, Mitsuo; Lee, H.-J.; Rodriguez, D.; Takahashi, Tone; Abbas, K.*; Bogucarska, T.*; Crochemore, J.-M.*; Pedersen, B.*; Varasano, G.*

61st Annual Meeting of the Institute of Nuclear Materials Management (INMM 2020), Vol.2, p.907 - 911, 2021/00

Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code

Aoki, Takeshi; Chirayath, S. S.*; Sagara, Hiroshi*

Annals of Nuclear Energy, 141, p.107325_1 - 107325_7, 2020/06

https://doi.org/10.1016/j.anucene.2020.107325

The proliferation resistance (PR) of an inert matrix fuel (IMF) in the transuranic nuclear fuel cycle (NFC) of a high temperature gas cooled reactor is evaluated relative to the uranium and plutonium mixed-oxide (MOX) NFC of a light water reactor using PRAETOR code and sixty-eight input attributes. The objective is to determine the impacts of chemical stability of IMF and fuel irradiation on the PR. Specific material properties of the IMF, such as lower plutonium content, carbide ceramics coating, and absence of U, contribute to enhance its relative PR compared to MOX fuel. The overall PR value of the fresh IMF (an unirradiated direct use material with a one-month diversion detection timeliness goal) is nearly equal to that of the spent MOX fuel (an irradiated direct use nuclear material with a three-month diversion detection timeliness goal). Final results suggest a reduced safeguards inspection frequency to manage the IMF.

Delayed gamma-ray spectroscopy, 2; Design study of moderator for a practical system

Rossi, F.; Rodriguez, D.; Takahashi, Tone; Seya, Michio; Koizumi, Mitsuo

Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (CD-ROM), 3 Pages, 2018/11

This paper (presentation) reports on the design study for seeking compactness of moderator (and reflector) structure for the Delayed Gamma-ray Spectroscopy Non Destructive Assay system to be applied for verification of fissile isotopic (Pu-239, Pu-241 and U-235) composition ratio in High Radioactive Nuclear Material sample such as dissolved solution of reprocessing facility. We first investigated advantages and disadvantages of using different compact neutron sources as DT and DD neutron generators. This led us to the conclusion of using DD sources to achieve a compact (and practical) NDA system. Based on MCNP simulations, with the use of a DD neutron generator, a preliminary optimization study was performed and will be shown here.