Thermally altered subsurface material of asteroid (162173) Ryugu

Kitazato, Kohei*; Milliken, R. E.*; Iwata, Takahiro*; Abe, Masanao*; Otake, Makiko*; Matsuura, Shuji*; Takagi, Yasuhiko*; Nakamura, Tomoki*; Hiroi, Takahiro*; Matsuoka, Moe*; et al.

Nature Astronomy (Internet), 5(3), p.246 - 250, 2021/03

https://doi.org/10.1038/s41550-020-01271-2

Here we report observations of Ryugu's subsurface material by the Near-Infrared Spectrometer (NIRS3) on the Hayabusa2 spacecraft. Reflectance spectra of excavated material exhibit a hydroxyl (OH) absorption feature that is slightly stronger and peak-shifted compared with that observed for the surface, indicating that space weathering and/or radiative heating have caused subtle spectral changes in the uppermost surface. However, the strength and shape of the OH feature still suggests that the subsurface material experienced heating above 300 C, similar to the surface. In contrast, thermophysical modeling indicates that radiative heating does not increase the temperature above 200 C at the estimated excavation depth of 1 m, even if the semimajor axis is reduced to 0.344 au. This supports the hypothesis that primary thermal alteration occurred due to radiogenic and/or impact heating on Ryugu's parent body.

Short- and middle-ranges order structures of KNbO nanocrystals

Yoneda, Yasuhiro; Kunisada, Ryoichi*; Chikada, Tsukasa*; Ueno, Shintaro*; Fujii, Ichiro*; Nagata, Hajime*; Ohara, Koji*; Wada, Satoshi*

Japanese Journal of Applied Physics, 58(SL), p.SLLA03_1 - SLLA03_7, 2019/11

https://doi.org/10.7567/1347-4065/ab37e2

Rapid uplifting of the northern part of Hida Mountain Range at 1 Ma, based on lithofacies and petrography in the Iyari Formation

Oikawa, Teruki; Wada, Hajime*

Chishitsugaku Zasshi, 110(9), p.528 - 535, 2004/09

None

Safety Characteristics of Mid-sized MOX Fueled Liquid Metal Reactor Core of High Converter Type in the Initiating Phase of Unprotected Loss of Flow Accident; Effects of low specific fuel power density on ULOF behavior brought by employment of large diameter fuel pins

Ishida, Masayoshi; Kawada, Kenichi; Niwa, Hajime

JNC TN9400 2003-059, 74 Pages, 2003/07

JNC-TN9400-2003-059.pdf:1.58MB

Safety characteristics in core disruptive accidents (CDAs) of mid-sized MOX fueled liquid metal reactor core of high converter type have been examined by using the CDA initiating phase analysis code SAS4A. The design concept of high converter type reactor core has been studied as one of options in the category of sodium-cooled reactor in Phase II of Feasibility Study on Commercialized Fast Reactor Cycle System.An unprotected loss-of-flow accident (ULOF) has been selected as a representative CDA initiator for this study. A core concept of high converter type, which employed a large diameter fuel pin of 11.1mm with 1.2m core height to get a large fuel volume fraction in the core to achieve high internal conversion ratio was proposed in JFY2001. Each fuel subassembly of the core (abbreviated here as UPL120) was provided with an upper sodium plenum directly above the core to reduce the sodium void reactivity worth. Because of the large fuel pin diameter, average specific fuel power density (31 kW/kg-MOX) of UPL120 is about one half of those of conventional large MOX cores. The reactivity worth of sodium voiding is 6$ in the whole core, and -1$ in the all upper plenums. Initiating phase of ULOF accident in UPL120 under the conditions of nominal design and best estimate analysis resulted in a slightly super-prompt critical power burst. The causes of the super-prompt criticality have been identified twofold: (a) the low specific fuel power density of core reduced the effectiveness of prompt negative reactivity feedback of Doppler and axial fuel expansion effects upon increase in reactor power, and (b) the longer core height compared with conventional 1m cores brought, together with the lower specific power density, a remarkable delay in insertion of negative fuel dispersion reactivity after the onset of fuel disruption in sodium voided subassembly due to the lower linear heat rating in the top portion of the core. During the delay, burst-type fuel failures in sodium un-v

An evaluation study on ULOF event sequences in the prototype FBR; An evaluation of CDA reflecting the latest knowledge

Tobita, Yoshiharu; Morita, Koji; Kawada, Kenichi; Niwa, Hajime; Nonaka, Nobuyuki

PNC TN9410 97-079, 106 Pages, 1997/09

PNC-TN9410-97-079.pdf:3.9MB

The sequences of ULOF (unprotected loss-of-flow) event in the prototype FBR has been evaluated, as a part of the research and development (R&D) in the reactor safety research, reflecting the latest experimental and analytical knowledge on CDA (core disruptive accident) which has been accumulated at O-arai Engineering Center. In the R&D activity on the FBR reactor safety subject, we have accumulated the experimental knowledge of mitigation mechanism in the energy generating process in CDA, utilizing international in-pile safety experimental programs such as CABRI program, as well as the out-of-pile experiments in Japan and foreign countries. This knowledge has been reflected to the development and validation of the SAS and SIMMER code. The objectives of this study are to apply these new assessment techniques to the prototype FBR and to clarify quantitatively in detail the energy generation process of CDA. In this study, an emphasis is placed on the event sequence of the melt progression phase ("transition phase") which has been recognized as one of the important issues of CDA analysis. The major parameters to be considered in this phase are the change of the mobile molten fuel mass and the history of the fuel motion, and also the relation between these parameters and energy generation mechanism. The following methods and approaches have been taken into account in this evaluation study. (a)The SAS4A code is used for the analysis of the transient behavior in the first Phase driven by core voiding ("initiating phase"), and the SIMMER-III code is used for the latter phases with melt-progression (tansition phase) and also the energy conversion process from the thermal one to the mechanical one. These codes have been developed and validated under the collaboration among PNC, CEA and FZK. (b)The uncertainty band of the void reactivity worth and Doppler coeficient has been reduced through the re-evaluation of the critical experimental data in the neutron physics area. ...

Spectra of solid laser materials for the small high intensity laser

Tajiri, Nobuhiro*; Hiroyasu, Tomoyuki*; Wada, Motoi*; Kenmotsu, Takahiro*; Kiriyama, Hiromitsu; Daito, Izuru; Sasao, Hajime*; Suzuki, Masayuki; Okada, Hajime

no journal, , 

no abstracts in English

Development of the anomalous small-angle X-ray scattering method at BL22XU

Tominaga, Aki; Oba, Yojiro; Shobu, Takahisa; Owada, Kenji*; Tanida, Hajime; Konno, Azusa; Morooka, Satoshi; Motokawa, Ryuhei; Kumada, Takayuki

no journal, , 

In steel materials, it is known that precipitation of Cr rich phase hardens ferrite phase and decreases toughness in base material. Small angle X-ray scattering is a promising method for analysis of this precipitation process because the precipitate is nanometer size. However, it is usually difficult to separate the scattering between the Fe phase and Cr phase since Fe and Cr are close in atomic number. Therefore, in order to observe the state of phase separation of Cr, we developed an anomalous X-ray small angle scattering (A-SAXS) method at BL22XU.