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Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi
no journal, ,
We developed uranium mass assay systems for 200-litter wastes drums applied neutron and 
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 -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 -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.
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.
Maeda, Toshikatsu; Omori, Hiroyuki*
no journal, ,
no abstracts in English
activity under highly alkaline conditionsSawaguchi, Takuma; Kadowaki, Mitsushi*; Mukai, Masayuki; Tsukada, Manabu; Maeda, Toshikatsu; Tanaka, Tadao
no journal, ,
no abstracts in English
Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi
no journal, ,
no abstracts in English
Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake
no journal, ,
no abstracts in English
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
Ohara, Takaharu; Ikeda, Makinori; Morishita, Masaki; Miyazaki, Masashi; Shimada, Koji; Moriizumi, Makoto*
no journal, ,
no abstracts in English
Harada, Tatsuyuki*; Okafuji, Takashi*; Morishita, Masaki; Tsukimori, Kazuyuki
no journal, ,
no abstracts in English
Omae, Takahiro; Kato, Masaaki*; Kanayama, Haruyuki*; Morishita, Masaki
no journal, ,
no abstracts in English
-ray NDA experiment at the Compact ERLHajima, Ryoichi; Hayakawa, Takehito; Seya, Michio; Kawata, Hiroshi*; Kobayashi, Yukinori*; Urakawa, Junji*
no journal, ,
no abstracts in English
-ray beams; Simulation of -ray generation and detectionHajima, Ryoichi; Hayakawa, Takehito; Kikuzawa, Nobuhiro
no journal, ,
no abstracts in English
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.
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.
Terada, Kazushi*; Iwamoto, Nobuyuki
no journal, ,
no abstracts in English
Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki
no journal, ,
no abstracts in English
Kofuji, Hirohide; Sawada, Nobuyuki*; Sasaki, Kazuya*; Amamoto, Ippei; Myochin, Munetaka; Suzuki, Akihiro*; Terai, Takayuki*
no journal, ,
The phosphate conversion process has been studied for reuse of spent electrolyte generated from pyrochemical reprocessing. As the fundamental information of thermodynamic data, heat capacities of some kind of phosphate were measured and phosphate conversion reactions were discussed based on such thermodynamic data.
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.
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.
Seki, Masayuki; Kihara, Yoshiyuki; Hirako, Kazuhito*; Motoki, Kazuhiko*; Tsukada, Tatsuya*
no journal, ,
no abstracts in English