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Journal Articles

Study of shields against D-T neutrons for Prompt Gamma-ray Analysis apparatus in Active-N

Furutaka, Kazuyoshi; Toh, Yosuke

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.297 - 304, 2020/10

Journal Articles

Non-destructive analysis of samples with a complex geometry by NRTA

Ma, F.; Kopecky, S.*; Alaerts, G.*; Harada, Hideo; Heyse, J.*; Kitatani, Fumito; Noguere, G.*; Paradela, C.*; $v{S}$alamon, L.*; Schillebeeckx, P.*; et al.

Journal of Analytical Atomic Spectrometry, 35(3), p.478 - 488, 2020/03

 Times Cited Count:0 Percentile:100(Chemistry, Analytical)

Journal Articles

Performance of large volume LaBr$$_{3}$$ scintillation detector equipped with specially-designed shield for neutron resonance capture analysis

Tsuchiya, Harufumi; Koizumi, Mitsuo; Kitatani, Fumito; Harada, Hideo

Nuclear Instruments and Methods in Physics Research A, 932, p.16 - 26, 2019/07

 Times Cited Count:0 Percentile:100(Instruments & Instrumentation)

Journal Articles

Development of active neutron NDA system for radioactive nuclear materials

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

Proceedings of INMM 60th Annual Meeting (Internet), 7 Pages, 2019/07

Journal Articles

Sample shape effect on nuclear material quantification with neutron resonance transmission analysis

Tsuchiya, Harufumi; Ma, F.; Kitatani, Fumito; Paradella, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*

Proceedings of 41st ESARDA Annual Meeting (Internet), p.374 - 377, 2019/05

Journal Articles

Neutron resonance transmission analysis for measurement of nuclear materials in nuclear fuel

Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*

Proceedings of INMM 59th Annual Meeting (Internet), 6 Pages, 2018/07

Journal Articles

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

Journal Articles

Delayed $$gamma$$-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

Koizumi, Mitsuo; Rossi, F.; Rodriguez, D.; Takamine, Jun; Seya, Michio; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences, 146, p.09018_1 - 09018_4, 2017/09

 Times Cited Count:2 Percentile:9.6

Journal Articles

Neutron resonance analysis for nuclear safeguards and security applications

Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Tsuchiya, Harufumi

EPJ Web of Conferences, 146, p.09002_1 - 09002_4, 2017/09

 Times Cited Count:3 Percentile:4.51

Journal Articles

R&D of active neutron NDA techniques for nuclear nonproliferation and nuclear security, 3; Validation of neutron transport code for design of NDA system

Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi; Bogucarska, T.*; Crochemore, J. M.*; Varasano, G.*; Pedersen, B.*

Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nippon Shibu Nenji Taikai Rombunshu (CD-ROM), 7 Pages, 2017/02

JAEA and EC/JRC are carrying out collaborative research to develop NDA techniques that can be utilized for quantification of high radioactive special nuclear materials such as spent fuel and next generation minor actinide fuels. In the research, reliability of neutron transport codes is important because it is utilized for design and development of a demonstration system of next-generation Differential Die-away (DDA) technique in JAEA. In order to evaluate the reliability, actual neutron flux distribution in a sample cavity was examined in PUNITA device using JRC type DDA technique and JAWAS-T device using JAEA type DDA technique, and then the measurement results were compared with the simulation results obtained by the neutron transport codes. The neutron flux distribution in the target matrix was also examined in the PUNITA and compared with the simulation results. We report on the measurement and simulation results of the neutron flux distribution and evaluation results of the reliability of the neutron transport codes.

Journal Articles

Comparison between simulation and experimental results for neutron flux in DDA systems

Maeda, Makoto; Komeda, Masao; Ozu, Akira; Kureta, Masatoshi; Toh, Yosuke; Bogucarska, T.*; Crochemore, J. M.*; Varasano, G.*; Pedersen, B.*

EUR-28795-EN (Internet), p.694 - 701, 2017/00

Journal Articles

Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security

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

EUR-28795-EN (Internet), p.684 - 693, 2017/00

Journal Articles

Delayed gamma-ray analysis for characterization of fissile nuclear materials

Koizumi, Mitsuo; Rossi, F.; Rodriguez, D.; Takamine, Jun; Seya, Michio; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EUR-28795-EN (Internet), p.868 - 872, 2017/00

Journal Articles

LaBr$$_3$$ $$gamma$$-ray spectrometer for detecting $$^{10}$$B in debris of melted nuclear fuel

Koizumi, Mitsuo; Tsuchiya, Harufumi; Kitatani, Fumito; Harada, Hideo; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; Schillebeeckx, P.*

Nuclear Instruments and Methods in Physics Research A, 837, p.153 - 160, 2016/11

 Times Cited Count:1 Percentile:82.75(Instruments & Instrumentation)

Journal Articles

Development of active neutron NDA techniques for nonproliferation and nuclear security, 2; Study on a compact NRTA system

Tsuchiya, Harufumi; Kitatani, Fumito; Maeda, Makoto; Kureta, Masatoshi

Proceedings of INMM 57th Annual Meeting (Internet), 6 Pages, 2016/07

From a viewpoint of nuclear safeguards and nuclear security, it has recently become important to develop a non-destructive assay (NDA) system that accurately determines the amount of special nuclear materials (SNMs) in various samples such as spent fuels, next generation MA-Pu fuels and fuel debris. One candidate of those NDA techniques is neutron resonance transmission analysis (NRTA). It relies on a neutron time-of-flight measurement and is a well-established method to apply for the accurate evaluations of nuclear data, including total cross sections and resonance parameters. The potential of NRTA to quantify SNM in complex materials has been already demonstrated by performing NRTA measurement at IRMM/GELINA under collaboration of JAEA and JRC. However, a present NRTA system usually has a large electron accelerator facility to generate intense neutrons, whereas this is very difficult to apply to various facilities that need to measure SNM. Therefore a compact NRTA system would be required for practical applications of quantifying SNM in a variety of samples. In order to realize a compact NRTA system, we are developing a prototype with a D-T neutron generator that has a pulse width of 10 $$mu$$s and an average maximum neutron yield ranging from $$10^{8}$$ n/s to $$2times10^{9}$$ n/s. Numerical calculations were used to optimize the system performance to quantify SNM and MA in spent and MA-Pu fuels. In this presentation, those numerical calculation results, together with a brief description of the prototype, are presented. In addition, we discuss a future prospect of a compact NRTA system equipped with a neutron source with a shorter pulse width (ex. 100 ns) and a more intense neutron yield.

Journal Articles

Evaluation of neutron flux distribution in the JAEA type and JRC type DDA systems

Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi; Bogucarska, T.*; Crochemore, J. M.*; Varasano, G.*; Pedersen, B.*

Proceedings of INMM 57th Annual Meeting (Internet), 9 Pages, 2016/07

The JAEA and EC/JRC have started collaborative research to develop a technique that can be utilized for quantification of high radioactive special nuclear materials such as next generation minor actinide fuels. In the study of a Differential Die-Away (DDA) technique, which is one of the techniques to be improved in the collaborative research, JRC type and JAEA type DDA techniques are compared. In the JRC type DDA technique, large amount of thermal neutron is generated using D-T neutron generator and graphite moderator to accomplish high detection sensitivity for small amount of fissile material. On the other hand, in JAEA type, relatively hard neutron spectrum and moderation of neutron in the target matrix are utilized to minimize position dependence of detection efficiency. Estimation of the neutron field is important to evaluate the performance of the system in DDA technique. The purpose of this study is to validate simulation results by experimental results and evaluate neutron flux distribution in the system by the simulation and the experiment. In this paper, we present the evaluation results of the neutron flux distributions in PUNITA which utilizes JRC type DDA technique and JAWAS-T which utilizes JAEA type DDA technique obtained by Monte Carlo simulation and activation method.

Journal Articles

Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security, 1; Study on next generation DDA

Kureta, Masatoshi; Maeda, Makoto; Ozu, Akira; Tobita, Hiroshi

Proceedings of INMM 57th Annual Meeting (Internet), 8 Pages, 2016/07

Under the collaboration program with EC Joint Research Center, we have carried out the R&D program "Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security" with DDA (Differential Die-away Analysis), NRTA, PGA / NRCA and DGS. In this paper, we presents the outline of the current activity and study on next generation DDA. The goal of this study is to establish the DDA technique for high radiation nuclear materials with small measurement uncertainty. Lastly simulation study on newly developed prototype system "Active-N" which will be constructed at JAEA/NUCEF/BECKY facility in 2017 is presented.

Journal Articles

Characteristics of neutron resonance densitometry, 2; Neutron resonance capture analysis

Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Kureta, Masatoshi; Becker, B.*; Kopecky, S.*; Heyse, J.*; Paradela, C.*; Mondelaers, W.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12

Neutron Resonance Densitometry (NRD) was developed as a non-destructive assay to quantify U and Pu isotopes in particle-like debris. NRD is composed of neutron resonance transmission analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA) or Prompt Gamma-ray Analysis (PGA). NRCA/PGA in NRD plays a role of identifying impurities in debris under the high-radiation field primarily caused by $$^{137}$$Cs. For this purpose, a novel LaBr$$_3$$ $$gamma$$-ray detector employing specific shields has been newly developed. With the developed $$gamma$$-ray detector, a demonstration NRCA experiment was performed at a neutron time of flight facility GELINA (Belgium). As a result, samples (Hf, Gd, Ni) placed in a black box that is completely sealed by third party were successfully identified by the experiment. This presentation explains the design concept of the $$gamma$$ ray detector including its detection principle and details of the demonstration NRCA experiment.

Journal Articles

Characteristics of neutron resonance densitometry, 1; Neutron resonance transmission analysis

Kitatani, Fumito; Harada, Hideo; Koizumi, Mitsuo; Tsuchiya, Harufumi; Kureta, Masatoshi; Becker, B.*; Kopecky, S.*; Heyse, J.*; Paradela, C.*; Mondelaers, W.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12

From 2012 to 2014, Neutron Resonance Densitometry (NRD) is being developed as a non-destructive assay to quantify U and Pu isotopes. NRD is composed of neutron resonance transmission analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA)/Prompt Gamma-ray Analysis (PGA). NRTA in NRD plays a role of quantifying the amounts of the isotopes of a nuclear fuel material (U, Pu) in molten fuel debris. Therefore, the neutron absorption measurement using Time-of-Flight (TOF) method is carried out. A demonstration NRTA experiment was performed at a neutron time of flight facility GELINA (Belgium). Consequently, we succeeded in iquantifying the randomly selected sample from Au, W, Rh, Nb, Cu. Co, Mn, B contained in a black box. In this presentation, we describe the principle of measurement of the developed NRTA and explain details of the demonstration experiment.

Journal Articles

Active neutron NDA techniques for nuclear non-proliferation applications, 1; Development plan

Kureta, Masatoshi; Koizumi, Mitsuo; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Seya, Michio

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12

The new program "Development of active neutron NDA techniques" has started for non-proliferation applications collaborating with EC-JRC. The final purpose of this program is to establish the measurement techniques for the high radioactive special nuclear material such as MA-Pu fuel for transmutation of minor actinide. In this program, the JAEA will conduct the R&D on active neutron non-destructive measurement techniques, DDA, NRTA, PGA/NRCA and DGS. The development plan and current status of the design study of the active neutron integrated test apparatus named "Active-N" are presented in this report.

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