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Journal Articles

Implementation of random sampling for ACE-format cross sections using FRENDY and application to uncertainty reduction

Kondo, Ryoichi*; Endo, Tomohiro*; Yamamoto, Akio*; Tada, Kenichi

Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019) (CD-ROM), p.1493 - 1502, 2019/00

A perturbation capability of ACE formatted cross section files was developed using the modules of FRENDY. Uncertainty quantification using MCNP was carried out for the Godiva critical experiment by the RS method. We verified the results of the RS method by comparing with those obtained by the conventional sensitivity analyses. Moreover, uncertainty reduction using the bias factor method with the RS technique was applied to kinetic parameter, i.e., neutron generation time.

Journal Articles

High-energy nuclear data uncertainties propagated to MYRRHA safety parameters

Stankovskiy, A.*; Iwamoto, Hiroki; $c{C}$elik, Y.*; Van den Eynde, G.*

Annals of Nuclear Energy, 120, p.207 - 218, 2018/10

 Times Cited Count:3 Percentile:42.25(Nuclear Science & Technology)

Propagation of high-energy (above 20-MeV) nuclear data uncertainties on the safety related neutronic responses in accelerator driven systems has been assessed. The total core power and production of radionuclides contributing to radiation source terms were focused on. The article features a method based on the Monte Carlo sampling of random nuclear data files from the covariance matrices generated from the sets of reaction cross sections obtained with model calculations of high-energy particle interactions with matter or picked up from already existing nuclear data libraries. It has been demonstrated that nuclear data uncertainties do not need to be propagated through particle transport calculations to obtain uncertainties on the responses. This advantage allowed to investigate the convergence of the sample average to the best estimate. The number of random nuclear data file sets needed to obtain reliable uncertainty on the total core power is around 300 that results in the uncertainty of 14%. The uncertainties on the concentrations of nuclides most important for the safety assessment that are accumulated in lead-bismuth eutectic during irradiation, range from 5 to 60%. Concentrations of some nuclides exemplified by Tritium converge much slower than neutron multiplicities so that several thousands of samples are needed to ensure reliable uncertainty estimates.

Journal Articles

Amount of radioactive cesium sedimentation in a soil saving dam with 3D laser scanner

Watanabe, Takayoshi; Oyama, Takuya; Ishii, Yasuo; Niizato, Tadafumi; Abe, Hironobu; Mitachi, Katsuaki; Sasaki, Yoshito

KEK Proceedings 2017-6, p.122 - 126, 2017/11

no abstracts in English

Journal Articles

Percolation fractal dimension in scattering line shapes of the random-field Ising model

Ye, F.*; Matsuda, Masaaki; Katano, Susumu; Yoshizawa, Hideki*; Belanger, D. P.*; Sepp$"a$l$"a$, E. T.*; Fernandez-Baca, J. A.*; Alava, M. J.*

Journal of Magnetism and Magnetic Materials, 272-276, p.1298 - 1299, 2004/05

 Times Cited Count:8 Percentile:56.54(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

High-energy X-ray diffraction of disordered materials in high-energy X-ray diffraction beamline BL04B2 at SPring-8

Kohara, Shinji*; Suzuya, Kentaro

Hoshako, 14(5), p.365 - 375, 2001/11

no abstracts in English

Journal Articles

High-energy X-ray diffraction studies of non-crystalline materials

Ono, Hideo; Kohara, Shinji*; Umesaki, Norimasa*; Suzuya, Kentaro

Journal of Non-Crystalline Solids, 293-295, p.125 - 135, 2001/11

 Times Cited Count:20 Percentile:29.1

no abstracts in English

JAEA Reports

Evaluation of the analytical errors jn plutonium and uranium isotopic composition analysis based on routine control measurement data (1998/9$$sim$$2000/12)

; ; ; ; ; *; *

JNC-TN8440 2001-005, 33 Pages, 2001/02

JNC-TN8440-2001-005.pdf:1.24MB

Four mass spectrometers are used for plutonium and uranium isotopic composition analysis in the Plutonium Fuel Center. Analytical errors of the analysis was evaluated based on routine control data obtained with measurement of reference materials. It was confirmed that the errors satisfied the International Target Values for safeguard analysis, and the random error of the analysis was improved by changing conventional method to total evaporation method.

Journal Articles

Level statistics for the quasiparticle spectra inside a two-dimensional vortex core with impurities

Fujita, Ayumi

Physical Review B, 62(22), p.15190 - 15194, 2000/12

 Times Cited Count:3 Percentile:75.73(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

None

*; *; *

JNC-TY8400 2000-006, 52 Pages, 2000/03

JNC-TY8400-2000-006.pdf:1.68MB

None

JAEA Reports

None

JNC-TJ4420 2000-002, 794 Pages, 2000/03

JNC-TJ4420-2000-002.pdf:23.42MB

no abstracts in English

Journal Articles

Structural physics at JAERI-BL-14B1 beam line

Mizuki, Junichiro; Konishi, Hiroyuki; Nishihata, Yasuo; Takahashi, Masamitsu; Suzuya, Kentaro; Matsumoto, Norimasa; Yoneda, Yasuhiro

Nippon Kessho Gakkai-Shi, 42(1), p.68 - 75, 2000/02

no abstracts in English

JAEA Reports

None

Sugihara, Yoichiro*; Mukai, Katsuyuki*; Nunomiya, Ichiro*

PNC-TJ6357 97-001, 40 Pages, 1997/03

PNC-TJ6357-97-001.pdf:1.52MB

None

JAEA Reports

None

PNC-TN7450 96-002, 77 Pages, 1996/05

PNC-TN7450-96-002.pdf:5.14MB

no abstracts in English

Journal Articles

Recovery of hydrogen isotopes and impurity mixture by cryogenic molecular sieve bed for GDC gas cleanup

Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Tanaka, Kenichi*; Uetake, Mitsuru*; Nishikawa, Masabumi*

Fusion Technology, 28(3), p.591 - 596, 1995/10

no abstracts in English

JAEA Reports

Data collection on the erosion rate of ground, 3

*; *; *

PNC-TJ7361 95-002, 217 Pages, 1995/03

PNC-TJ7361-95-002.pdf:15.4MB

None

Journal Articles

Structural changes of poly(3-hydroxybutyrate-co-3-hydroxyvalerate) fractionated with acetone-water solution

Mitomo, Hiroshi*; Morishita, Norio; *

Polymer, 36(13), p.2573 - 2578, 1995/00

 Times Cited Count:46 Percentile:12.26

no abstracts in English

JAEA Reports

None

PNC-TN1311 94-009, 14 Pages, 1994/09

no abstracts in English

JAEA Reports

None

; Yoneda, Shigeo*; Koyakaichi, Minoru*

PNC-TJ7308 93-005, 292 Pages, 1993/03

PNC-TJ7308-93-005.pdf:6.95MB

no abstracts in English

JAEA Reports

Journal Articles

Determination of hot spot factors for thermal and hydraulic design of High Temperature Engineering Test Reactor (HTTR)

Maruyama, So; Murakami, Tomoyuki*; Fujii, Sadao*; Fujimoto, Nozomu; Tanaka, Toshiyuki; Sudo, Yukio; Saito, Shinzo

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.425 - 430, 1991/00

no abstracts in English

35 (Records 1-20 displayed on this page)