JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-14 displayed on this page of 14
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Uncertainty quantification of $$^{237}$$Np, $$^{241}$$Am, and $$^{243}$$Am reaction rates in highly enriched uranium fuel cores at Kyoto University Critical Assembly

Pyeon, C. H.*; Oizumi, Akito; Katano, Ryota; Fukushima, Masahiro

Nuclear Science and Engineering, 199(3), p.429 - 444, 2025/03

https://doi.org/10.1080/00295639.2024.2380624
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

Experimental analyses of neptunium-237 ($$^{237}$$Np), americium-241 ($$^{241}$$Am), and $$^{243}$$Am fission and $$^{237}$$Np capture reaction rates are conducted by the Serpent 2 code together with ENDF/B-VIII.0 and JENDL-5, using experimental data at neutron spectra of thermal and intermediate regions obtained in the solid-moderated and solid-reflected cores with highly-enriched uranium fuel at the Kyoto University Critical Assembly. Also, uncertainty quantification of fission and capture reaction rate ratios of test samples of $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$Am with reference samples of uranium-235 ($$^{235}$$U) and gold-197 ($$^{197}$$Au) are evaluated by the MARBLE code system. In terms of fission reaction rate ratios of $$^{237}$$Np/$$^{235}$$U, $$^{241}$$Am/$$^{235}$$U and $$^{243}$$Am/$$^{235}$$U, a comparison between experiments and Serpent 2 calculations shows an accuracy about 5, 15 and 10%, respectively, together with ENDF/B-VIII.0 and JENDL-5. For capture reaction rate ratios of $$^{237}$$Np/$$^{197}$$Au, Serpent 2 calculations reveal a fairly good accuracy at the thermal neutron spectrum. The total uncertainties of $$^{237}$$Np/$$^{235}$$U, $$^{241}$$Am/$$^{235}$$U and $$^{243}$$Am/$$^{235}$$U fission reaction rate ratios by MARBLE with the covariance data of ENDF/B-VIII.0 and JENDL-5 are found to be about 4% at most in all cores, except for about 8% of $$^{243}$$Am/$$^{235}$$U with ENDF/B-VIII.0 at the intermediate neutron spectrum.

JAEA Reports

Development of the versatile reactor analysis code system, MARBLE3

Yokoyama, Kenji; Hazama, Taira; Taninaka, Hiroshi; Oki, Shigeo

JAEA-Data/Code 2024-007, 41 Pages, 2024/10

JAEA-Data-Code-2024-007.pdf:1.1MB

The third version of the versatile reactor analysis code system, MARBLE3, has been developed. In the development of the former version of MARBLE, object-oriented scripting language Python (Python2) had been used and then the latest version of Python (Python3) was released. However, due to its backward incompatibility, MARBLE no longer worked with Python3. For this reason, MARBLE3 has been fully modified and maintained to work with Python3. In MARBLE3, newly developed analysis codes and newly proposed calculation methods were incorporated, and the user interface was extended and solvers were reimplemented for maintainability, extensibility, and flexibility. In MARBLE3, the three-dimensional hexagonal/triangular transport code MINISTRI Ver.7 (MINISTRI7) and the three-dimensional hexagonal/triangular diffusion code D-MINISTRI are available as the new analysis codes. These codes can be used in the neutronics analysis system SCHEME and the fast reactor burnup analysis system OPRHEUS, which are the subsystems of MARBLE. In addition, the user interface of CBG, a core analysis system embedded in MARBLE, was extended so that the diffusion and transport calculation solvers for the 2-dimensional RZ system of CBG can be used on SCHEME. On the other hand, MARBLE3 has extended the functionality of the burnup calculation solver so that it can use the numerical methods proposed in the papers on the improvement of the Chebyshev rational function approximation method and the minimax polynomial approximation method. From the viewpoint of maintainability, the point reactor kinetics solver POINTKINETICS, which was introduced in MARBLE2, has been newly reworked as the KINETICS solver in MARBLE3.

Journal Articles

Magnetic layer thickness influence on magnetoelastic properties anisotropy in Co$$_{2}$$Fe$$_{0.4}$$Mn$$_{0.6}$$Si heusler alloy thin films

Nabialek, A.*; Chumak, O.*; Seki, Takeshi*; Takanashi, Koki; Baczewski, L. T.*; Szymczak, H.*

IEEE Transactions on Magnetics, 59(11), p.2501405_1 - 2501405_5, 2023/11

https://doi.org/10.1109/TMAG.2023.3287324
 Times Cited Count：2 Percentile：28.34(Engineering, Electrical & Electronic)

Journal Articles

Influence of the strain effect on magnetocrystalline anisotropy in Co$$_{2}$$Fe$$_{0.4}$$Mn$$_{0.6}$$Si Heusler alloys

Nabialek, A.*; Chumak, O. M.*; Aleshkevych, P.*; Domagala, J. Z.*; Pacewicz, A.*; Salski, B.*; Krupka, J.*; Seki, Takeshi*; Takanashi, Koki; Baczewski, L. T.*; et al.

Scientific Reports (Internet), 13, p.17016_1 - 170169, 2023/10

https://doi.org/10.1038/s41598-023-43979-x
 Times Cited Count：4 Percentile：47.87(Multidisciplinary Sciences)

Journal Articles

Superconducting fluctuation effect on epitaxially layered films of superconductor NbN and half-metallic Heusler alloy Co$$_{2}$$MnSi

Shigeta, Iduru*; Oku, Shuta*; Kubota, Takahide*; Kimura, Shojiro*; Seki, Takeshi*; Shinozaki, Bunju*; Awaji, Satoshi*; Takanashi, Koki; Hiroi, Masahiko*

AIP Advances (Internet), 13(2), p.025116_1 - 025116_5, 2023/02

https://doi.org/10.1063/9.0000584
 Times Cited Count：1 Percentile：12.23(Nanoscience & Nanotechnology)

Journal Articles

Mechanisms of action of radon therapy on cytokine levels in normal mice and rheumatoid arthritis mouse model

Kataoka, Takahiro*; Naoe, Shota*; Murakami, Kaito*; Yukimine, Ryohei*; Fujimoto, Yuki*; Kanzaki, Norie; Sakoda, Akihiro; Mitsunobu, Fumihiro*; Yamaoka, Kiyonori*

Journal of Clinical Biochemistry and Nutrition, 70(2), p.154 - 159, 2022/03

https://doi.org/10.3164/jcbn.21-91
 Times Cited Count：3 Percentile：20.55(Nutrition & Dietetics)

JAEA Reports

Development of the versatile reactor analysis code system, MARBLE2

Yokoyama, Kenji; Jin, Tomoyuki; Hirai, Yasushi*; Hazama, Taira

JAEA-Data/Code 2015-009, 120 Pages, 2015/07

JAEA-Data-Code-2015-009.pdf:1.93MB

The second version of the versatile reactor analysis code system, MARBLE2, has been developed. A lot of new functions have been added inMARBLE2 by using the base technology developed in the first version (MARBLE1). Introducing the remaining functions of the conventional code system (JOINT-FR and SAGEP-FR), MARBLE2 enables one to execute almost all analysis functions of the conventional code system with the unified user interfaces of its subsystem, SCHEME. In particular, the sensitivity analysis functionality is available in MARBLE2. On the other hand, new built-in solvers have been developed, and existing ones have been upgraded. Furthermore, some other analysis codes and libraries developed in JAEA have been consolidated and prepared in SCHEME. In addition, several analysis codes developed in the other institutes have been additionally introduced as plug-in solvers. Consequently, $$gamma$$-ray transport calculation and heating evaluation become available. As for another subsystem, ORPHEUS, various functionality updates and speed-up techniques have been applied based on user experience of MARBLE1 to enhance its usability.

Journal Articles

RERTR-2004, International Meeting on Reduced Enrichment for Research and Test Reactors

Nakagome, Yoshihiro*; Shimizu, Kenichi

Kaku Busshitsu Kanri Senta Nyusu, 34(2), p.14 - 19, 2005/02

RERTR(Reduced Enrichment for Research and Test Reactors) for 2004 was held at IAEA in Vienna of Austria, An author and Professor Nakagome(Kyoto University) attended this internationalmeeting and the author presented "Status of Reduced Enrichment Program for Research Reactors in Japan" with Dr.Nakagome. JNMCC(Japan Nuclear Material Control Center) requested to present a report of 2004 RERTR international Meeting and related content for the author and Dr.Nakagome. the content of the report described the meeting content and related issue which related US FRR SNF(Foregin Reserach Reactors Spent Nuclear Fuels) Acceptance Program.

Journal Articles

Orbital angular momentum and interpretation of core-absorption magnetic circular dichroism on the band picture in Co-based Heusler alloys Co$$_{2}Y$$Sn ($$Y$$=Ti, Zr, and Nb)

Yamasaki, Atsushi*; Imada, Shin*; Arai, Ryuji*; Utsunomiya, Hiroshi*; Suga, Shigemasa*; Muro, Takayuki*; Saito, Yuji; Kanomata, Takeshi*; Ishida, Shoji*

Physical Review B, 65(10), p.104410_1 - 104410_6, 2002/03

https://doi.org/10.1103/PhysRevB.65.104410
 Times Cited Count：63 Percentile：89.39(Materials Science, Multidisciplinary)

The magnetic circular dichroism (MCD) of core-level absorption [x-ray absorption spectroscopy (XAS)] spectra in the soft x-ray region has been measured for the ferromagnetic Heusler alloys Co$$_{2}$$TiSn, Co$$_{2}$$ZrSn, and Co$$_{2}$$NbSn. The many-peak structures which are clearly observed in the Co 2p-3d XAS-MCD spectra cannot be well explained by atomic multiplet calculations but are better explained by the Co 3d unoccupied states predicted by linear muffin-tin orbital atomic sphere approximation band structure calculations. The MCD spectra show an obvious contribution of the orbital angular momentum component to the magnetic moment in these alloys. The ratio between the orbital angular momentum and spin derived from the MCD spectra varies by more than a factor of 2 within these alloys. The mechanism of this variation is discussed in comparison with the band structure calculations.

Journal Articles

$$omega$$-like diffraction anomaly in the premartensitic $$beta$$$$_{1}$$ phase of AuCuZn$$_{2}$$ alloy

; ; Morii, Yukio; ; Katano, Susumu; Funahashi, Satoru; H.R.Child*

Mater. Trans. JIM, 32(11), p.1011 - 1016, 1991/00

https://doi.org/10.2320/matertrans1989.32.1011
 Times Cited Count：4 Percentile：47.48(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

None

PNC TN1420 91-001, 258 Pages, 1990/11

PNC-TN1420-91-001.pdf:9.24MB

no abstracts in English

JAEA Reports

CCS-I, A Code to analyze a dynamic behavior of uranium enrichment process in a centrifuge cascade; An Application to the safeguards effectiveness assessment

Okamoto, Tsuyoshi*; Nishimura, Hideo

JAERI-M 90-031, 89 Pages, 1990/02

JAERI-M-90-031.pdf:2.22MB

no abstracts in English

Journal Articles

Effectiveness of safeguards in a centrifuge enrichment plant

Nishimura, Hideo; Okamoto, Tsuyoshi*

31st Annual Meeting Proc. of Nuclear Materials Management,Vol. 19, p.518 - 523, 1990/00

no abstracts in English

JAEA Reports

Benchmark Calculation on Nuclear Characteristics of JRR-4 HZU Core by SRAC Code System

Arigane, Kenji

JAERI-M 87-063, 133 Pages, 1987/04

JAERI-M-87-063.pdf:3.46MB

no abstracts in English

14 (Records 1-14 displayed on this page)
  • 1