Development of the Unified Cross-section Set ADJ2017

Yokoyama, Kenji; Sugino, Kazuteru; Ishikawa, Makoto; Maruyama, Shuhei; Nagaya, Yasunobu; Numata, Kazuyuki*; Jin, Tomoyuki*

JAEA-Research 2018-011, 556 Pages, 2019/03

JAEA-Research-2018-011.pdf:19.53MB
JAEA-Research-2018-011-appendix1(DVD-ROM).zip:433.07MB
JAEA-Research-2018-011-appendix2(DVD-ROM).zip:580.12MB
JAEA-Research-2018-011-appendix3(DVD-ROM).zip:9.17MB

We have developed a new unified cross-section set ADJ2017, which is an improved version of the unified cross-section set ADJ2010 for fast reactors. The unified cross-section set is used for reflecting information of C/E values (analysis / experiment values) obtained by integral experiment analyses; the values are stored in the standard database for FBR core design via the cross-section adjustment methodology, which integrates with the information such as uncertainty (covariance) of nuclear data, uncertainty of integral experiment / analysis, sensitivity of integral experiment with respect to nuclear data. The ADJ2017 is based on Japan's latest nuclear data library JENDL-4.0 as in the previous version of ADJ2010, and it incorporates more information on integral experimental data sets related to minor actinides (MAs) and degraded plutonium (Pu). In the creation of ADJ2010, a total of 643 integral experimental data sets were analyzed and evaluated, and 488 of the integral experimental data sets were finally selected to be used for the cross-section adjustment. In contrast, we have evaluated a total of 719 data sets, and eventually adopted 620 integral experimental data sets to create ADJ2017. ADJ2017 shows almost the same performance as ADJ2010 for the main neutronic characteristics of conventional sodium-cooled MOX-fuel fast reactors. In addition, for the neutronic characteristics related to MA and degraded Pu, ADJ2017 improves the C/E values of the integral experimental data sets, and reduces the uncertainty induced by the nuclear data. ADJ2017 is expected to be widely used in the analysis and design research of fast reactors. Moreover, it is expected that the integral experimental data sets used for ADJ2017 can be utilized as a standard database of FBR core design.

Development of a fast reactor for minor actinides transmutation; Improvement of prediction accuracy for MA-related integral parameters based on cross-section adjustment technique

Yokoyama, Kenji; Maruyama, Shuhei; Numata, Kazuyuki; Ishikawa, Makoto; Takeda, Toshikazu*

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.1906 - 1915, 2016/05

Modeling of failure phenomena in rocks induced by stress concentration(Phase 2)

Toriihara, Makoto*; Maruyama, Makoto*; Suzuki, Kenichiro*; Namiki, Kazuto*

JNC TJ7400 2005-034, 179 Pages, 2004/02

JNC-TJ7400-2005-034.PDF:31.02MB

Elucidation of the physichal process leading to brittle failure in crystalline rocks and modeling its mechanism is of fundamental importance in evaluating the mechanical and hydraulic properties of EDZ. In this study, Granitic rock columns and plates with circular opening were subjected to triaxial compression and tension tests and measured elastic wave velocity and resisitivity to analyze nucleation and growth of microcracks. The following conclusions were important to note that: (1)During 90% to 100% stress levels to failure stress, it appear that cracks grew on their size but no cracks were nucleated. (2)It was demonstrated that crack tensor F was closely related the second rank tensor V which was determined by measuring elastic wave velocity on at least six direction. (3)The applicability of numerical analysis model based on the micromechanics was introduced. This could be considered the mechanism of the damage growth (microcrack growth) and the interaction among microcracks. (4)On the experiment of Granitic rock plates with circular opening, the process leading to brittle failure and damage growth of the rock around the opening were observed with AE monitoring and so on. (5)In order to evaluate the variety of permeability with the damage growth, it was showed that permeability tensor in terms of crack tensor gave the permeability change in stress history.

None

Maruyama, Makoto*; Toriihara, Makoto*; Mikami, Tetsuji*; Hata, Koji*

JNC TJ7400 2005-030, 106 Pages, 2003/02

JNC-TJ7400-2005-030.PDF:50.79MB

no abstracts in English

Development of advanced reprocessing system using high selective and controllable precipitants

Noda, Kyoko*; Takao, Koichiro*; Sugiyama, Yuichi*; Harada, Masayuki*; Nogami, Masanobu*; Maruyama, Koichi*; Takahashi, Hiroaki*; Kim, S.-Y.; Sato, Makoto; Mineo, Hideaki; et al.

no journal, , 

We have been developing an advanced reprocessing system for spent FBR fuels based on precipitation method using pyrrolidone derivatives. In previous investigation, N-cyclohexyl-2-pyrrolidone (NCP) is used as a precipitant, which is able to precipitate selectively UO ions in HNO solution, and a process consisting of two separation steps; selective U precipitation step and U-Pu co-precipitation step, was developed. In order to make the process more effective and more economical, we are now studying precipitation of U and Pu with other pyrrolidone derivatives. The outline of the study and main results obtained until now are shown in this presentation.