Update of fire receiver panel (The Waste Safety Testing Facility)

Hatakeyama, Yuichi; Hirai, Koki; Ikegami, Yuta*; Sano, Naruto; Tomita, Takeshi; Usami, Koji; Tagami, Susumu

JAEA-Technology 2024-020, 33 Pages, 2025/03

JAEA-Technology-2024-020.pdf:2.21MB

The Waste Safety Testing Facility (WASTEF) is a facility that began operation in December 1982 with the aim of conducting safety testing research on the long-term storage and subsequent geological disposal of high-level radioactive waste generated by the reprocessing of spent fuel. This facility is composed of five concrete cells, one lead cell, six glove boxes, and seven hoods, and is a large-scale facility capable of using nuclear fuel materials including uranium and plutonium, as well as radioisotopes such as neptunium and americium. The facility is equipped with an automatic fire alarm system for the entire building in accordance with the Fire Service Act and regulations on technical standards for facilities used. This is an important aspect of safety management, and it is required that the equipment be sufficiently sound and reliable. However, after more than 30 years of use since its installation, the fire receiving panel, one of the components of the automatic fire alarm system, has deteriorated significantly. Furthermore, many of the parts used have been discontinued and are no longer available, making it difficult to procure them, making it difficult to maintain the equipment's performance. Therefore, in order to ensure the safe and stable operation of WASTEF, the fire receiving panel was updated. This report summarizes the update of the fire receiving panel among the automatic fire alarm equipment that was implemented in FY2022.

Utilization of gamma ray irradiation at the WASTEF Facility

Sano, Naruto; Yamashita, Naoki; Watanabe, Masaya; Tsukada, Manabu*; Hoshino, Kazutoyo*; Hirai, Koki; Ikegami, Yuta*; Tashiro, Shinsuke; Yoshida, Ryoichiro; Hatakeyama, Yuichi; et al.

JAEA-Technology 2023-029, 36 Pages, 2024/03

JAEA-Technology-2023-029.pdf:2.47MB

At the Waste Safety Testing Facility (WASTEF), the gamma ray irradiation device "Gamma Cell 220" was relocated from the 4th Research Building of the Nuclear Science Research Institute in FY2019, and the use of gamma ray irradiation has begun. Initially, Fuel Cycle Safety Research Group, Fuel Cycle Safety Research Division, Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness, the owner of this device, conducted the tests as the main user, but since 2022, other users, including those outside the organization, have started using it. The gamma ray irradiation device "Gamma Cell 220" is manufactured by Nordion International Inc. in Canada. Since it was purchased in 1989, the built-in Co radiation source has been updated once, and safety research related to nuclear fuel cycles, etc. It is still used for this purpose to this day. This report summarizes the equipment overview of the gamma ray irradiation device "Gamma Cell 220", its permits and licenses at WASTEF, usage status, maintenance and inspection, and future prospects.

Optimization of an isothermal gas-chromatographic setup for the chemical exploration of dubnium (Db, Z = 105) oxychlorides

Chiera, N. M.; Sato, Tetsuya; Tomitsuka, Tomohiro; Asai, Masato; Ito, Yuta; Shirai, Kaori*; Suzuki, Hayato; Tokoi, Katsuyuki; Toyoshima, Atsushi; Tsukada, Kazuaki; et al.

Journal of Radioanalytical and Nuclear Chemistry, 320(3), p.633 - 642, 2019/06

https://doi.org/10.1007/s10967-019-06505-w

An isothermal gas-chromatographic (IGC) device has been developed and tested for on-line gas phase studies of volatile oxychlorides of short-lived group-5 transition metals. Radioisotopes of niobium and tantalum, produced in nuclear fusion evaporation reactions, are directly flushed into the IGC setup by an inert gas-jet. Oxychloride compounds are formed by the addition of SOCl and O. Parameters influencing the formation and transport of NbOCl and TaOCl are investigated. For nuclides with half-lives () of about 30 s, an overall efficiency of 7% is obtained, rendering the IGC setup suitable for the chemical exploration of Db( = 34s).

Present status of manufacturing and R&Ds for the JT-60SA tokamak

Higashijima, Satoru; Kamada, Yutaka; Barabaschi, P.*; Shirai, Hiroshi; JT-60SA Team

Fusion Science and Technology, 68(2), p.259 - 266, 2015/09

https://doi.org/10.13182/FST15-108

Role of low order rational -values in the ITB events in JT-60U reverse shear plasmas

Neudatchin, S. V.*; Takizuka, Tomonori; Hayashi, Nobuhiko; Isayama, Akihiko; Shirai, Hiroshi; Fujita, Takaaki; Kamada, Yutaka; Koide, Yoshihiko; Suzuki, Takahiro

Nuclear Fusion, 44(9), p.945 - 953, 2004/09

https://doi.org/10.1088/0029-5515/44/9/002

The formation of internal transport barriers (ITBs) near =2,3 surfaces in normal shear (NrS) discharges of JT-60U and JET is known. In reverse shear (RS) JT-60U plasmas, the role of minimum () equal to 3.5,3,2.5,2 is not obvious for ITB formation. In this paper, the effect of low rational values on ITB-events in JT-60U NrS and RS plasmas is investigated. Under sufficient neutral beam power (8MW for 1.2-1.5MA/3.8T pulses), ITB-events are seen at rational and non-rational values of . The space-time evolutions of and are similar, suggesting the same mechanism for and transports. The temporal formation of stronger ITB under passing =3 (after periodical improvements and degradations via ITB-events) in RS H-mode with =8MW is presented. Under smaller power, ITB-events are observed only at rational values. In a weak RS shot with =4MW, the abrupt rise of is seen at =3.5, while more cases of rise are observed. The difference between the and evolutions for the low power suggests the decoupling of and transports.

Properties of internal transport barrier formation in JT-60U

Sakamoto, Yoshiteru; Suzuki, Takahiro; Ide, Shunsuke; Koide, Yoshihiko; Takenaga, Hidenobu; Kamada, Yutaka; Fujita, Takaaki; Fukuda, Takeshi; Takizuka, Tomonori; Shirai, Hiroshi; et al.

Nuclear Fusion, 44(8), p.876 - 882, 2004/08

https://doi.org/10.1088/0029-5515/44/8/006

Response of the ion thermal diffusivity to the radial electric field Er shear has been investigated in JT-60U and the following results were found. (1) In the case of positive magnetic shear (PS) plasma, the ion thermal diffusivity in the core region shows L mode state, weak internal transport barrier (ITB), and strong ITB depending upon the heating power. In the case of reversed magnetic shear (RS) plasma, however, no power degradation of the ion thermal diffusivity is observed. (2) In the case of weak ITB, the ion thermal diffusivity decreases gradually with increasing the Er shear for both PS and RS plasmas. There exists a threshold of an effective Er shear to change its state from weak to strong ITBs. (3) The threshold of the effective Er shear in the case of RS plasma is small compared with that in the case of PS plasma.

Impact of toroidal rotation on ELM behaviour in the H-mode on JT-60U

Sakamoto, Yoshiteru; Shirai, Hiroshi; Fujita, Takaaki; Ide, Shunsuke; Takizuka, Tomonori; Oyama, Naoyuki; Kamada, Yutaka

Plasma Physics and Controlled Fusion, 46(5A), p.A299 - A304, 2004/05

https://doi.org/10.1088/0741-3335/46/5A/033

no abstracts in English

Studies on the In-Situ Experiments with Respect to Disposal Engineering in Horonobe Underground Research Laboratory

Kurihara, Yuji; Yui, Mikazu; Tanai, Kenji; Kawakami, Susumu; Sugita, Yutaka; Taniguchi, Naoki; Hirai, Takashi

JNC TN8400 2004-002, 58 Pages, 2004/04

JNC-TN8400-2004-002.pdf:2.38MB

In this paper, the items of in-situ experiments at Horonobe URL with respect to the technical issues about reliability of long-term behavior of engineered barrier system were extracted. And the concepts of the experiments were studied from several points of view such as verification of models and getting the actual behavior. Extracted items of the in-situ experiments are as follows. Coupled Phenomena Test (THMC Test), Buffer & Rock Creep Test, Gas Migration Test, Over-pack Corrosion Test, High-pH Influence Test, Low Alkaline Concrete Execution Test, Engineering-Barrier Emplacement Test, Tunnel Plugging Test.

Instantaneous correlation between ELM-like MHD activity and abrupt non-local reduction of transport at internal transport barrier formation in JT-60U high- plasmas

Neudatchin, S.*; Takizuka, Tomonori; Hayashi, Nobuhiko; Isayama, Akihiko; Shirai, Hiroshi; Fujita, Takaaki; Kamada, Yutaka; Koide, Yoshihiko; Ito, Kimitaka*; Miura, Yukitoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(12), p.1218 - 1220, 2003/12

http://ci.nii.ac.jp/naid/10012479213

New type of edge-core instantaneous interplay in JT-60U high- plasmas is found. Abrupt in time and wide in space reduction of electron heat flux in the core (called ITB-event) is correlated in ms timescale with the start of an ELM. This result gives a hint of the control to form the ITB immedeately and non-locally by inducing the ELM-like MHD activity.

Stiff temperature profiles in JT-60U ELMy H-mode plasmas

Mikkelsen, D. R.*; Shirai, Hiroshi; Urano, Hajime*; Takizuka, Tomonori; Kamada, Yutaka; Hatae, Takaki; Koide, Yoshihiko; Asakura, Nobuyuki; Fujita, Takaaki; Fukuda, Takeshi*; et al.

Nuclear Fusion, 43(1), p.30 - 39, 2003/01

https://doi.org/10.1088/0029-5515/43/1/304

The stiffness of thermal transport in ELMy H-modes is explained in a series of carefully chosen JT-60U plasmas, and measured temperature are compared with the predictions of several transport models. A heating power scan with constant Tped, a scan of pedestal temperature Tped with constant heating power, and an on/off-axis heating comparison are presented. Predictions of the RLWB and IFS/PPPL models generally agree with the measured temperature outside 0.3, but the Multimode model uniformly predicts temperatures that are too high except in the central region.