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JAEA Reports

Training using JMTR and related facilities in FY2021 and FY2022

Nakano, Hiroko; Fujinami, Kyoko; Yamaura, Takayuki; Kawakami, Jun; Hanakawa, Hiroki

JAEA-Review 2023-036, 33 Pages, 2024/03

JAEA-Review-2023-036.pdf:2.47MB

A practical training course using the JMTR (Japan Materials Testing Reactor) and other research infrastructures was held from November 29 to December 2 in 2021 for Asian young researchers and engineers. This course was adopted as International Youth Exchange Program in Science (SAKURA SCIENCE Exchange Program) which is the project of the Japan Science and Technology Agency, and this course aims to enlarge the number of high-level nuclear researchers/engineers in Asian countries which are planning to introduce a nuclear power plant, and to promote the use of facilities in future. In this year, from the viewpoint of preventing the spread of COVID-19 infection, it was decided to hold the event online. 53 young researchers and engineers joined the course from 6 countries. In FY2022, training programs with invitations were held due to the easing of restrictions on entry into Japan from overseas. 7 young researchers and engineers from4 Asian countries participated in the training from February 1 to 10, 2023.The common curriculum in the training course of FY2021 and FY2022 included lectures on nuclear energy, irradiation testing, safety management, JMTR decommissioning plan, etc. In the online session, conducted in FY2021, information exchange on the energy situation in each country was conducted. On-site training conducted in FY2022, included practical training on operation using simulations, environmental monitoring, etc. and facility tours of the JMTR, etc. Many participants could join the online training course, they created a diversity of expertise and made lively discussions during the information exchange. On-site training, while limited in number of participants, provided a good opportunity for personnel exchange through practical training and face-face communication. It is desirable to hold on-site training as long as circumstances permit. This report summarizes the training conducted in FY2021 and FY2022.

JAEA Reports

On-site training using JMTR and related facilities in FY2019

Nakano, Hiroko; Nishikata, Kaori; Nagata, Hiroshi; Ide, Hiroshi; Hanakawa, Hiroki; Kusunoki, Tsuyoshi

JAEA-Review 2022-073, 23 Pages, 2023/01

JAEA-Review-2022-073.pdf:2.02MB

A practical training course using the JMTR (Japan Materials Testing Reactor) and other research infrastructures was held from July 24th to July 31st in 2019 for Asian young researchers and engineers. This course was adopted as Japan-Asia Youth Exchange Program in Science (SAKURA Exchange Program in Science) which is the project of the Japan Science and Technology Agency, and this course aims to enlarge the number of high-level nuclear researchers/engineers in Asian countries which are planning to introduce a nuclear power plant, and to promote the use of facilities in future. In this year, 12 young researchers and engineers joined the course from 6 countries. This course consists of lectures, which are related to irradiation test research, safety management of nuclear reactors, nuclear characteristics of the nuclear reactors, etc., practical training such as practice of research reactor operation using simulator and technical tour of nuclear facilities on nuclear energy. The content of this course in FY 2019 is reported in this paper.

Journal Articles

Decommissioning plan of the Fukushima Daiichi Nuclear Power Station and CPD of the nuclear and radiation professional engineers for Fukushima support activity

Sasaki, Satoru

Gijutsushi, 28(8), p.8 - 11, 2016/08

AA2016-0156.pdf:1.53MB

This serialization article will describe Continuing Professional Development (CPD) of the nuclear and radiation professional engineers for Fukushima support activity after the Fukushima Daiichi Nuclear Power Station accident. In this first article, the structure and the outline of the serialization are noticed. Based on the lecture of CPD, issues and risks of the decommissioning plan of the Fukushima Daiichi Nuclear Power Station are manifested.

JAEA Reports

Development of an on-site plant analyzer (1); Development of a GUI for building plant models for analyzes and retrieval of real-time plant data

JNC TN4400 2000-002, 33 Pages, 2000/06

JNC-TN4400-2000-002.pdf:5.22MB

An on-site plant analyzer can provide analysis support in evaluating plant dynamic characteristics when unplanned events occur in a nuclear power station. The plant analyzer contains a plant-dynamics analysis code, which efficiently and quickly analyzes the plant dynamic characteristics. Elements being developed for the on-site plant analyzer include utilities to build plant models for performing analyses and to retrieve plant operation data. The addition of these elements to the analysis code supports the plant-dynamics analysis works in MONJU, in particular, to assist the analyses of start up tests. The system contains the FBR plant-dynamics analysis code "Super-COPD", which is based on the "COPD" code that was used in the safety licensing of MONJU. One feature of the system is that all operations, e.g., assembling plant models for analysis, are prepared using a GUI (Graphical user Interface). In addition to this feature, the system is able to retrieve directly on- and off-line plant data from MIDAS, the Monju Integrated Data Acquisition System. These plant data are used to supply time-dependent boundary conditions for the plant analysis models. For this report, two case studies were performed. First, the analysis result of a turbine trip test at 40% power operation using the full plant model is described. For the second, performance of the IHX model was evaluated using retrieved plant data for boundary conditions. With the development of this system, improvement in the efficiency of analyses of MONJU start-up tests is expected.

Oral presentation

JAEA's R&D activities for Fukushima environmental recovery including their application to on-site issues

Miyahara, Kaname

no journal, , 

This presentation focuses on JAEA's R&D for enhancing Fukushima off-site environmental recovery to address the needs for better scientific and technological capabilities to assess, predict, and minimize the impact of radiological contamination and illustrate how to enhance the understanding of radiation and associated risks in the public. Application of methods and technologies obtained by these R&D to on-site issues is also illustrated.

Oral presentation

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