Development of 0.5 mm gauge size radial collimators for high-pressure neutron diffraction experiments at PLANET in J-PARC

Hattori, Takanori; Suzuki, Koji*; Miyo, Tatsuya*; Ito, Takayoshi*; Machida, Shinichi*

Nuclear Instruments and Methods in Physics Research A, 1059, p.168956_1 - 168956_9, 2024/02

https://doi.org/10.1016/j.nima.2023.168956

Radial collimators (RC) with a 0.5 mm gauge size (GS) were specially designed for high-pressure neutron diffraction experiments and their performance and efficacy were investigated. The RCs with nominal GS of 0.75 mm, 1.5 mm, and 3.0 mm effectively exhibited GS of 0.50 mm, 1.07 mm, and 2.78 mm, respectively. The transmissions of all three RCs were almost equivalent. The assessment using a P-E press and a DAC revealed that the anvil scattering was considerably minimized and the sample-to-anvil signal ratio reached values of 0.5 and 2.0 for the PE press and DAC, respectively, when using the 0.5 mm-GS RCs. These results indicate that the 0.5mm-GS RCs have been fabricated as intended and exhibit efficacy for the high-pressure-neutron diffraction experiments, specifically those exceeding 30 GPa. Among those ever manufactured for neutron scattering experiments, the RCs display the smallest GS.

Installation manuals for "Utsusemi"

Inamura, Yasuhiro

JAEA-Testing 2023-002, 80 Pages, 2023/12

JAEA-Testing-2023-002.pdf:2.43MB

"Utsusemi" is a suite of software used to process data obtained from measurements of neutron scattering experiments at the Materials and Life Science Experimental Facility (MLF), J-PARC. To directly obtain the physical quantities which scientists want to get from the data produced by instruments at MLF, many processes are required, such as creating histogram format data, easily visualizing and converting units and correcting intensity adapting the instrument conditions. "Utsusemi" software consists of many software components, many functions for data processing, graphical interface software for executing Utsusemi functions, data visualization applications, and so on. "Utsusemi" has already played an important role in data processing and has been widely employed in MLF beamlines. This document describes how to install the "Utsusemi" software on each operating system to be of help of instrument staff and users who want to process data by themselves. Installation of "Utsusemi" on Windows and macOS requires only general knowledge of working with PC applications according to this document.

Study on criticality safety control of fuel debris for validation of methodology applied to the safety regulation

Suyama, Kenya; Ueki, Taro; Gunji, Satoshi; Watanabe, Tomoaki; Araki, Shohei; Fukuda, Kodai; Yamane, Yuichi; Izawa, Kazuhiko; Nagaya, Yasunobu; Kikuchi, Takeo; et al.

Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 6 Pages, 2023/10

To remove and store safely the fuel debris generated by the severe accident of the Fukushima Daiichi Nuclear Power Station in 2011 is one of the most important and challenging topics for decommissioning of the damaged reactors in Fukushima. To validate the adopted method for the evaluation of criticality safety control of the fuel debris through comparison with the experimental data obtained by the criticality experiments, the Nuclear Regulation Authority (NRA) of Japan funds a research and development project which was entrusted to the Nuclear Safety Research Center (NSRC) of Japan Atomic Energy Agency (JAEA) from 2014. In this project, JAEA has been conducting such activities as i) comprehensive computation of the criticality characteristics of the fuel debris and making database (criticality map of the fuel debris), ii) development of new continuous energy Monte Carlo code, iii) evaluation of criticality accident and iv) modification of the critical assembly STACY for the experiments for validation of criticality safety control methodology. After the last ICNC2019, the project has the substantial progress in the modification of STACY which will start officially operation from May 2024 and the development of the Monte Carlo Code "Solomon" suitable for the criticality calculation for materials having spatially random distribution complies with the power spectrum. We present the whole picture of this research and development project and status of each technical topics in the session.

Planning of the debris-simulated critical experiments on the new STACY

Gunji, Satoshi; Araki, Shohei; Arakaki, Yu; Izawa, Kazuhiko; Suyama, Kenya

Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 9 Pages, 2023/10

JAEA has been modifying a critical assembly called STACY from a solution system to a light-water moderated heterogeneous system to validate computation results of criticality characteristics of fuel debris generated in the accident at TEPCO's Fukushima Daiichi Nuclear Power Station. To experimentally simulate the composition and characteristics of fuel debris, we will prepare several grid plates which make particular neutron moderation conditions and a number of rod-shaped concrete and stainless-steel materials. Experiments to evaluate fuel debris's criticality characteristics are scheduled using these devices and materials. This series of STACY experiments are planned to measure the reactivity of fuel debris-simulated samples, measure the critical mass of core configurations containing structural materials such as concrete and stainless steels, and the change in critical mass when their arrangement becomes non-uniform. Furthermore, two divided cores experiments are scheduled that statically simulate fuel debris falling, and also scheduled that subcriticality measurement experiments with partially different neutron moderation conditions. The experimental plans have been considered taking into account some experimental constraints. This paper shows the schedule of these experiments, as well as the computation results of the optimized core configurations and expected results for each experiment.

Debris-simulated core analysis under fuel procurement constraints in new STACY experiments

Araki, Shohei; Gunji, Satoshi; Arakaki, Yu; Yoshikawa, Tomoki; Murakami, Takahiko; Kobayashi, Fuyumi; Izawa, Kazuhiko; Suyama, Kenya

Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 8 Pages, 2023/10

New experiments simulating fuel debris in the new criticality assembly, STACY, are designed to contribute to the validation of criticality calculations for criticality control of the fuel debris in the Fukushima Daiichi Nuclear Power Plant accident. In the new STACY experiment, a two-region core consisting of a driver region and a test region was investigated in order to configure a debris-simulated core with under-moderation condition (lattice pitch 1.27-cm) having the constraint of available fuel rod number. The test region with a 1.27-cm lattice pitch is surrounded by the driver region, in which fuel rods are arranged in a checkerboard pattern on a 1.27-cm lattice plate, with a 1.80-cm lattice pitch. Neutron spectra and sensitivity were calculated by using MCNP6 and ENDF/B-VII. The core which has a 1717 test region with 373 fuel rods is the largest two-region core under the constraint. It was found that the core which has a 1717 test region can simulate the neutron spectra of under-moderation condition in a 1313 region inside the test region with the root-mean square percentage error of less than 5%. It was also confirmed that the sensitivity of Si and Ca (n,) reactions when the concrete simulant, was loaded could be simulated.

JAEA's action on medical RI production using research reactor

Arai, Masaji; Maeda, Shigetaka

Rinsho Hoshasen, 68(10), p.963 - 970, 2023/10

Ac-225 is attracting attention as an alpha-emitting medical radioisotope. Since its demand is expected to increase, domestic production of Ac-225 is required from the viewpoint of Japan's medical research and economic security. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity that can be produced in the experimental fast reactor Joyo and designed the concept that upgrades the existing facilities for transporting the irradiated target from Joyo to a neighboring PIE facility rapidly. Efficient Actinium-225 Separation from Ra-226 irradiated in a fast reactor was studied. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.

Development of experimental core configurations to clarify k variations by nonuniform core configurations

Gunji, Satoshi; Araki, Shohei; Suyama, Kenya

Nuclear Science and Engineering, 197(8), p.2017 - 2029, 2023/08

https://doi.org/10.1080/00295639.2022.2164151

The fuel debris generated by the accident at the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Plant is expected to have not only heterogeneous but also nonuniform compositions. Similarly, damaged fuel assemblies remaining in the reactor vessels also have nonuniform configurations due to some missing fuel rods. This non-uniformity may cause changing neutron multiplication factors. The effect of non-uniformity on the neutron multiplication factor is clarified by computations, and the possibility of experimentally validating the computations used for criticality management is being investigated. For this purpose, in this study the criticality effects of several core configurations of a new critical assembly, STACY, of the Japan Atomic Energy Agency with nonuniform arrangements of uranium oxide fuel rods, concrete rods, and stainless-steel rods were studied to confirm benchmarking potential. The difference in these arrangements changed the neutron multiplication factor by more than 1 $. We confirmed that changes in local neutron moderation conditions and the clustering of specific components caused this effect. In addition, the feasibility of benchmark experimental cores with nonuniform arrangements is evaluated. If benchmarking of such experiments could be realized, it would help to validate calculation codes and to develop criticality management methods by machine learning.

Advanced thermal-hydraulic experiments and instrumentation for heavy liquid metal reactors

Pacio, J.*; Van Tichelen, K.*; Eckert, S.*; Wondrak, T.*; Di Piazza, I.*; Lorusso, P.*; Tarantino, M.*; Daubner, M.*; Litfin, K.*; Ariyoshi, Gen; et al.

Nuclear Engineering and Design, 399, p.112010_1 - 112010_15, 2022/12

https://doi.org/10.1016/j.nucengdes.2022.112010

Heavy-liquid metals (HLMs), such as lead and lead-bismuth eutectic (LBE), are proposed as primary coolants in accelerator driven systems and next-generation fast reactors. In Europe, the reference systems using HLMs are MYRRHA (LBE) and ALFRED (lead). This article presents an overview of recent experiences and ongoing activities on pool-type and loop-type HLM experiments. Pool tests include the measurement of forced- and natural-circulation flow patterns in several scenarios representative of nominal and decay heat removal conditions. Loop tests are focused on the evaluation of specific components, like mockups of the fuel assembly, control rod and heat exchangers. They involve the measurement of global variables, such as flow rate and pressure difference, and local quantities like temperature, velocity and vibrations. Advanced instrumentation, capable of sustaining high temperatures and corrosion, is necessary for accurate measurements, often in compact geometries. In addition to traditional techniques, other instrumentation based on optical fibers, ultrasonic and electromagnetic methods are discussed.

Completion of JENDL-5 and prospects for its application to numerical analysis, 4; Integral test of JENDL-5; Benchmark analysis in fast reactor system

Yokoyama, Kenji; Taninaka, Hiroshi

Kaku Deta Nyusu (Internet), (132), p.25 - 33, 2022/06

http://www.aesj.or.jp/~ndd/ndnews/pdf132/No132-04.pdf

This article explains the results of integral test of JENDL-5 by benchmark analysis in fast reactor system, which were presented in a special session of the 2022 Spring Annual Meeting of the Atomic Energy Society of Japan (AESJ). The latest version of Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. In order to confirm the applicability of JENDL-5 to the fast reactor system, we conducted a set of benchmark analysis using the integral experiment data included in the fast reactor nuclear design database which is being developed by JAEA. With respect to major nuclear characteristics in the standard fast reactor system, it was confirmed that the ratios of analysis result and experimental result (C/E values) based on JENDL-5 were almost the same as those of JENDL-4.0. In the special session, the results of sensitivity analysis were reported. Since the results have been described in the proceedings of the AESJ meeting, we add the results of the versions under development of JENDL-5 and discuss their relationship with the reported results of sensitivity analysis.

Proceedings of the 2020 Symposium on Nuclear Data; November 26-27, 2020, RIKEN Nishina Center, RIKEN Wako Campus, Wako, Saitama, Japan

Imai, Nobuaki*; Otsu, Hideaki*

JAEA-Conf 2021-001, 236 Pages, 2022/03

JAEA-Conf-2021-001.pdf:48.06MB

The 2020 Symposium on Nuclear Data was held on-site at RIBF Conference Hall in RIKEN Wako campus on November 26 to 27, 2020, combined with on-line connection conference. The symposium was organized by the Nuclear Data Division of the Atomic Energy Society of Japan (AESJ) in cooperation with Sigma Investigative Advisory Committee of AESJ, Nuclear Science and Engineering Center of Japan Atomic Energy Agency (JAEA), RIKEN Nishina Center, Center for Nuclear Study, The University of Tokyo (CNS), KEK Wako Nuclear Science Center (WNSC), School of Science, The University of Tokyo. In the symposium, six sessions were proposed and held: "Reactor theory and experiments" as a tutorial, "Accelerator Facilities and Nuclear Data", "Deep/Machine Learning and Nuclear Physics, Application to Nuclear Data", "Nuclear Medicine and Nuclear Pharmacy", "Fission, Heavy Ion Nuclear Spectroscopy", and "Nuclear Reaction Data" as lecture and discussion sessions. In addition, recent research progress on experiments, nuclear theory, evaluation, benchmark and applications were presented in the poster session. The total number of participants was 119, of which 62 were on-site participants. Each oral and poster presentation was followed by an active question and answer session. This report consists of total 40 papers including 15 oral and 25 poster presentations.