CIELO collaboration summary results; International evaluations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.

Nuclear Data Sheets, 148, p.189 - 213, 2018/02

https://doi.org/10.1016/j.nds.2018.02.003

The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - U, U, Pu, Fe, O and H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.

ERRORF; A Code to calculate covariance of self-shielding factor and its temperature gradient

Otsuka, Naohiko*; Zukeran, Atsushi*; Takano, Hideki*; Chiba, Go; Ishikawa, Makoto

JAEA-Data/Code 2008-012, 17 Pages, 2008/06

JAEA-Data-Code-2008-012.pdf:1.31MB

A computer code, ERRORF, was developed for calculation of covariance of self-shielding factor and its temperature gradient. This code is based on several modules. With this code, covariance of self-shielding factor and its temperature gradient can be calculated from evaluated nuclear library in the ENDF format.

Training report of the FBR cycle training facility in 2004FY

Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; Sasaki, Kazuichi; Sawada, Makoto

JNC TN4440 2005-001, 40 Pages, 2005/07

JNC-TN4440-2005-001.pdf:1.85MB

no abstracts in English

Training report of the FBR cycle training facility in 2004FY

Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; SASAKI, Kazuhito; Sawada, Makoto

JNC TN4410 2004-003, 20 Pages, 2004/07

JNC-TN4410-2004-003.pdf:0.66MB

The FBR cycle training facility consists of sodium handling training facility and maintenance training facility, and is being contributed to train for the operators and maintenance workers of the prototype fast breeder reactor "Monju". So far, some training courses have been added to the both training courses of sodium handling technologies maintenance technologies in every year in order to carry out be significant training for preparation of Monju restarting. As encouragement of the sodium handling technology training in 2003FY, the sodium heat transfer basic course was equipped as the 9th sodium handling training course with the aims of learning basic principal technology regarding sodium heat transfer. While, for the maintenance training course, a named "Monju Systems Learning Training Course", which aims to learn necessary knowledge as the engineers related Monju development, was provided newly in this year as an improvement concerned the maintenance course. In 2003FY, nine sodium handling technology training courses were carried out total 33 times and 235 trainees took part in those training courses. Also, nine training courses concerning the maintenance technology held 15 times and total 113 trainees participated. On the other hand, the 4th special lecture related sodium technology by France sodium school instructor was held on Mar. 15-17 and 34 trainees participated. Consequently, a cumulative trainees since October in 2000 opened the FBR cycle training facility reached to 1,236 so for.

None

Otsuka, Jiro; Kawanishi, Tomotake*; Koyagishi, Naoki; Sasaki, Kazuichi; Sawada, Makoto

JNC TN4410 2003-009, 31 Pages, 2003/12

JNC-TN4410-2003-009.pdf:0.75MB

None

A New coil current control system of the JT-60 toroidal field coil power supply

Matsukawa, Makoto; Omori, Yoshikazu; Totsuka, Toshiyuki; Furukawa, Hiroshi*

Heisei-10-Nen Denki Gakkai Sangyo Oyo Bumon Zenkoku Taikai Koen Rombunshu, p.103 - 106, 1998/00

no abstracts in English

JT-60 Plasma Control System

Kurihara, Kenichi; Kimura, Toyoaki; Yonekawa, Izuru; ; Matsukawa, Makoto; ; Kawamata, Yoichi; Totsuka, Toshiyuki; Akasaka, Hiromi; Sakata, Shinya

Fusion Engineering and Design, 11, p.441 - 454, 1990/00

no abstracts in English

Report on radiation control of TRACY

Masuyama, Koichi; Arakawa, Yuto; Otsuka, Yoshikazu; Yokosuka, Yoshiyuki; Kobayashi, Makoto; Akiyama, Isamu; Shimizu, Isamu

no journal, , 

no abstracts in English

Study on release and transport of aerial radioactive materials in reprocessing plant, 7; Hot test

Yamane, Yuichi; Amano, Yuki; Yanagida, Yoshinori; Kawasaki, Yasushi; Sato, Makoto; Hayasaka, Hiromi; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Ueda, Yoshinori*; et al.

no journal, , 

The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. This paper describes an experiment using a small test device having an electric furnace, in which 100 mL of the HALW was heated from room temperature to 300C and the amount of materials released during heating was measured. The amount of materials as a function of its initial concentration in the HALW is reported.

Density measurements of molten SUS316, Fe and Ni using an electromagnetic levitation technique under a static magnetic field

Watanabe, Makoto*; Higashi, Hideo*; Sasaki, Minako*; Adachi, Masayoshi*; Otsuka, Makoto*; Fukuyama, Hiroyuki*; Nishi, Tsuyoshi; Yamano, Hidemasa

no journal, , 

In this study, as a first step, density of the stainless steel 316 (SUS316), pure Fe and Ni were measured. For all samples, the densities are expressed with a linear function of temperature.