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Oral presentation

Feasibility study on material creation and new-type fuel utilization by using HTTR, 1; Outline of feasibility study

Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*

no journal, , 

As collaborative research project by Japan Atomic Energy Agency, Toyota Tsusho Corporation and Nuclear Fuel Industries, Ltd., new utilizations of HTGR and new R&D of a cooperative relationship between car industries and HTGR are presented. Specifically, we showed the results of feasibility study on material creation and new-type fuel utilization by using HTTR.

Oral presentation

Replacement of filter casing in the vessel ventilation of HAW storage process at the Tokai reprocessing plant

Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Decommissioning Project of Uranium Conversion Plant, 1; Decommissioning result (The First half of F.Y. 2010)

Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake

no journal, , 

no abstracts in English

Oral presentation

Status of development of a 500 kV photo-cathode electron gun for the next generation ERL light sources

Nishimori, Nobuyuki; Nagai, Ryoji; Hajima, Ryoichi; Yamamoto, Masahiro*; Miyajima, Tsukasa*; Honda, Yosuke*; Kuriki, Masao*; Iijima, Hokuto*; Kuwahara, Makoto*; Okumi, Shoji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Feasibility study on fabrication of MOX fuel pellet by blending recycle powder with granulated powder

Mizuno, Mineo; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki

no journal, , 

The short process is considered to be a main concept which has high feasibility in Fast Reactor Cycle Technology Development (FaCT). In this study, a small-scale fabrication test was carried out to investigate characteristic of MOX pellet made of granulated MOX powder blended with dry-route recycle powder, for the first time, as a basic test concern with the short process. As the results, it was found that the sintered density of the pellet clearly depends on the preparing conditions and content of recycle powder. The results is intended to be utilized in the investigation of engineering-scale test conditions.

Oral presentation

Proposal of a $$gamma$$-ray NDA experiment at the Compact ERL

Hajima, Ryoichi; Hayakawa, Takehito; Seya, Michio; Kawata, Hiroshi*; Kobayashi, Yukinori*; Urakawa, Junji*

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Reactor physics on STACY heterogeneous core with light water moderator, 3; Evaluation of kinetics in reactivity insertion events

Aoyama, Yasuo; Komuro, Michiyasu; Seki, Masakazu; Izawa, Kazuhiko; Sono, Hiroki; Ogawa, Kazuhiko; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Mizunami Underground Research Laboratory Project, 1; Status of construction and research & development

Sato, Toshinori; Saegusa, Hiromitsu; Hama, Katsuhiro; Ogata, Nobuhisa; Mikake, Shinichiro

no journal, , 

Japan Atomic Energy Agency has been conducting Mizunami Underground Research Laboratory (URL) Project aiming to establish a firm scientific basis for safe geological disposal including: establishing investigation techniques, analysis and assessment of the deep geological environment, and applicability assessment of engineering technologies for designing and constructing underground facilities. This report describes the construction status of the URL, the results of deep geological investigations carried out, and the future plan of this project.

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi; Terai, Takayuki*; et al.

no journal, , 

Three and half years has been passed from the start of IFMIF/EVEDA. In IFMIF/EVEDA, tasks for Lithium Target System consists of 5 validation tasks (LF1-5) and a design task (ED3), and are shared by Japan and Europe. Japan is covering the construction and operation of EVEDA Li Test Loop (LF1), diagnostics (LF2), purification system (LF4), remote handling system (LF5) and engineering design (ED3) with the contribution from universities. The present status of these tasks will be reported in the conference.

Oral presentation

Evaluation of nuclear data on Pd isotopes

Terada, Kazushi*; Iwamoto, Nobuyuki

no journal, , 

no abstracts in English

Oral presentation

Investigation of HTO transport in the environment using SPEEDI-MP's coupling calculation for material circulation

Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki

no journal, , 

no abstracts in English

Oral presentation

Tritium control technology in Fugen

Ishikura, Yasuji

no journal, , 

no abstracts in English

Oral presentation

Investigation of release characteristics of Kr gas arising in the reprocessing process

Otani, Takehisa; Suzuki, Kazuyuki; Hata, Katsuro; Kikuchi, Hideki; Nakamura, Daishi; Samoto, Hirotaka; Tanaka, Yukiyoshi

no journal, , 

The investigation of the behavior of krypton gas arising due to reprocessing of spent fuels has been performed at TRP. The whole amount of Kr gas transfers to the off-gas system through shearing and dissolution process, so it is applicable as an indicator to determine the progress of fuel dissolution. It is thought that the behavior of gaseous fission product, including Kr, in the spent fuels depends on burn-up and the type of spent fuels. In the reprocessing process, these deference are reflected to the migration rate of krypton gas between shearing off-gas system (SOG) and dissolver off-gas system (DOG). At TRP, four types of spent fuels (LWR; PWR, BWR and ATR; UO$$_{2}$$, MOX) were treated and examined about their release characteristics of krypton gas in order to understand the effect on burn-up and type of spent fuels. In this report, the results concerning the ATR-UO$$_{2}$$ fuel and ATR-MOX fuel are discussed compared with the results of LWR fuel.

Oral presentation

Estimation of probability distribution depending on magnitude of sodium leak event postulated in PSA, 2

Kurisaka, Kenichi; Takamatsu, Misao; Martin, L.*

no journal, , 

This study aims to quantify the probability distribution of the leak flow rate when a sodium leak event takes place, in terms of the effectiveness evaluation of accident management measures using probabilistic safety assessment. For this purpose, sodium leak instances that were experienced in domestic and foreign sodium-cooled fast reactor systems were investigated and analyzed. In most of these leak instances, individual total leak amount is known, but the leak duration time is unknown. Therefore, the previous study needed to assume the leak duration time as a probability distribution to estimate the leak flow rate. In this study, for more realistic evaluation, we investigated both total leak amount and leak duration time of sodium leak instances that were experienced in the Phenix reactor system. For 12 instances where total leak amount was already known, leak duration time became clear. Five leak instances were newly added. The probability distribution of the leak duration time was statistically analyzed by using these data. As a result, it became possible to quantify more realistically the probability distribution of the leak flow rate.

Oral presentation

Development of component reliability database for LMFBRs

Naruto, Kenichi*; Kurisaka, Kenichi

no journal, , 

This study aims to implement a probabilistic safety assessment (PSA) based on the component operating experience in sodium-cooled fast reactors (SFR). For this purpose, we developed the component reliability database for LMFBRs named CORDS and evaluated the failure rate for SFR PSA using CORDS. The reliability data of 33 years and 15 years have been accumulated in CORDS from Joyo and Monju, respectively. Baysian method was applied to the failure rate evaluation. This evaluation was classified into three cases by considering applicable data amount: (1) when sufficient data of the target plant is available, conventional Bayesian update was applied by using its own data and non-informative prior; (2) when sufficient data of similar plants is available, parametric empirical Baysian method was applied; (3) when sufficient data is not available, conventional Bayesian update was implemented by using all data. This study served to evaluate the failure rate for Monju PSA.

Oral presentation

On performance experience and measurements with Ningyo Waste Assay System (NWAS)

Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi

no journal, , 

We developed uranium mass assay systems for 200-litter wastes drums applied neutron and $$gamma$$ measurements by NDA method. In this intermediate report we will describe measurement systems and trial data. The systems are composed of the 16 pieces of helium-3 proportional counters for neutron detection and a large sized NaI(Tl) scintillation detector for $$gamma$$-ray detection. The extensive testing trials using the calibrated uranium sources with different enrichment and some kinds of matrices in drums were performed. Through the one year testing the useful experiences of this system concerning neutron and $$gamma$$-ray measurements for uranium mass were obtained. Almost all instruments and software were so good performance as is designed. As the next step we are going to schedule to try measurements for actual wastes that are stored in the Uranium Refining and Conversion Plant at Ningyo-toge, and put practical uses near future. Our research was accomplished with the support of Los Alamos National Laboratory.

267 (Records 1-20 displayed on this page)