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Journal Articles

Neutron importance estimation via new recursive Monte Carlo method for deep penetration neutron transport

Tuya, D.; Nagaya, Yasunobu

Nuclear Science and Engineering, 15 Pages, 2023/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

In Monte Carlo neutron transport calculations for local response or deep penetration problems, some estimation of an importance function is generally required in order to improve their efficiency. In this work, a new recursive Monte Carlo (RMC) method, which is partly based on the original RMC method, for estimating an importance function for local variance reduction (i.e., source-detector type) problems has been developed. The new RMC method has been applied to two sample problems of varying degrees of neutron penetrations, namely a one-dimensional iron slab problem and a three-dimensional concrete-air problem. The biased Monte Carlo calculations with variance reduction parameters based on the obtained importance functions by the new RMC method have been performed to estimate detector responses in these problems. The obtained results are in agreement with those by the reference unbiased Monte Carlo calculations. Furthermore, the biased calculations offered an increase in efficiency on the order of 1 to 10$$^{4}$$ in terms of the figure of merit (FOM). The results also indicated that the efficiency increased as the neutron penetration became deeper.

Journal Articles

Estimation method of systematic uncertainties in Monte Carlo particle transport simulation based on analysis of variance

Hashimoto, Shintaro; Sato, Tatsuhiko

Journal of Nuclear Science and Technology, 56(4), p.345 - 354, 2019/04

 Times Cited Count:5 Percentile:48.99(Nuclear Science & Technology)

Particle transport simulations based on the Monte Carlo method have been applied to shielding calculations. Estimation of not only statistical uncertainty related to the number of trials but also systematic one induced by unclear physical quantities is required to confirm the reliability of calculated results. In this study, we applied a method based on analysis of variance to shielding calculations. We proposed random- and three-condition methods. The first one determines randomly the value of the unclear quantity, while the second one uses only three values: the default value, upper and lower limits. The systematic uncertainty can be estimated adequately by the random-condition method, though it needs the large computational cost. The three-condition method can provide almost the same estimate as the random-condition method when the effect of the variation is monotonic. We found criterion to confirm convergence of the systematic uncertainty as the number of trials increases.

JAEA Reports

TIARA annual report 2003

Advanced Radiation Technology Center

JAERI-Review 2004-025, 374 Pages, 2004/11

JAERI-Review-2004-025-p0001-p0116.pdf:20.67MB
JAERI-Review-2004-025-p0117-p0247.pdf:21.34MB
JAERI-Review-2004-025-p0248-p0374.pdf:23.39MB

This annual report describes research and development activities which have been performed with the JAERI TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities from April 1, 2003 to March 31, 2004. Summary reports of 115 papers and brief descriptions on the status of TIARA in the period are contained. A list of publications, the type of research collaborations and organization of TIARA are also given as appendices.

Journal Articles

Evaluation of shutdown $$gamma$$-ray dose rates around the duct penetration by three-dimensional Monte Carlo decay $$gamma$$-ray transport calculation with variance reduction method

Sato, Satoshi; Iida, Hiromasa; Nishitani, Takeo

Journal of Nuclear Science and Technology, 39(11), p.1237 - 1246, 2002/11

 Times Cited Count:27 Percentile:83.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Proceedings of the Symposium on the Joint Research Project between JAERI and Universities; Status and Perspective of the Advanced Radiation Technology Project, January 27, 1999, National Education Center, Tokyo, Japan

Committee for the Joint Research Project on the Advanced Radiation Technology; Committee for the Collaborative Research on the Advanced Radiation Technology

JAERI-Conf 2000-008, 113 Pages, 2000/06

JAERI-Conf-2000-008.pdf:11.5MB

no abstracts in English

Journal Articles

Shielding analysis and evaluation of JRR-2 decommissioning

Iwashita, Mitsushige*; Arigane, Kenji; Kishimoto, Katsumi; Seiki, Y.*; Fukumura, Nobuo*; Mio, K.*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.372 - 378, 2000/03

no abstracts in English

Journal Articles

Characteristics of shielding design calculation for the SPring-8 synchrotron radiation beamlines

Asano, Yoshihiro; Sasamoto, Nobuo

Radiation Protection Dosimetry, 82(3), p.167 - 174, 1999/00

 Times Cited Count:9 Percentile:57.23(Environmental Sciences)

no abstracts in English

JAEA Reports

Design of ITER shielding blanket

Furuya, Kazuyuki; Sato, Satoshi; Hatano, Toshihisa; *; Kitamura, Kazunori*; Miura, H.*; *; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 97-022, 113 Pages, 1997/05

JAERI-Tech-97-022.pdf:3.42MB

no abstracts in English

Journal Articles

Shielding analysis for toroidal field coils around exhaust duct in fusion experimental reactors

Sato, Satoshi; Takatsu, Hideyuki; *; Seki, Yasushi

J. Fusion Eng. Des., 30(3), p.1076 - 1080, 1996/12

no abstracts in English

JAEA Reports

Journal Articles

Importance determination method for geometry splitting with Russian roulette in Monte Carlo calculations of thick and complicated core shielding structure

Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku

Journal of Nuclear Science and Technology, 32(10), p.971 - 980, 1995/10

 Times Cited Count:2 Percentile:28.12(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Transient thermal and stress analyses of the ITER shielding blanket/first wall under off-normal conditions

Furuya, Kazuyuki; Hashimoto, T.*; Sato, Satoshi; Kuroda, Toshimasa*; *; Kurasawa, Toshimasa; *; Takatsu, Hideyuki

JAERI-Tech 95-045, 53 Pages, 1995/09

JAERI-Tech-95-045.pdf:3.13MB

no abstracts in English

JAEA Reports

Radiation shielding safety guidebook; Elementary volume

JAERI-Tech 94-036, 226 Pages, 1994/12

JAERI-Tech-94-036.pdf:6.38MB

no abstracts in English

JAEA Reports

Pre-analyses of SS316 and SS316/Water bulk shielding experiments

Konno, Chikara; Maekawa, Fujio; *; Kosako, Kazuaki*; Ikeda, Yujiro; Oyama, Yukio; Maekawa, Hiroshi

JAERI-Tech 94-019, 43 Pages, 1994/10

JAERI-Tech-94-019.pdf:1.64MB

no abstracts in English

Journal Articles

Reactor shielding design of the High Temperature Engineering Test Reactor; Design analysis and shielding characteristics

Shindo, Ryuichi; Murata, Isao; Sawa, Kazuhiro; Shiozawa, Shusaku; *; Mori, Tomoaki*

Proc. of the 8th Int. Conf. on Radiation Shielding, p.351 - 358, 1994/00

no abstracts in English

Journal Articles

Reactor shielding design of the High Temperature Engineering Test Reactor; Application of 3-dimensional Monte Carlo code MCNP to shielding analysis for thick and complicated structure

Murata, Isao; Shindo, Ryuichi; Shiozawa, Shusaku

Proc. of the 8th Int. Conf. on Radiation Shielding, p.365 - 370, 1994/00

no abstracts in English

Journal Articles

Network parallel computing of Monte Carlo shielding analysis code MCACE by using shared files

P.I.Yazid*;

Journal of Nuclear Science and Technology, 30(12), p.1299 - 1302, 1993/12

 Times Cited Count:0 Percentile:0.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Comparison between measured and design dose rate equivalents on board of nuclear ship Mutsu

; Sakamoto, Yukio

Journal of Nuclear Science and Technology, 30(9), p.926 - 945, 1993/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Installation and execution of criticality and radiation shielding analysis codes on engineering work station

Masukawa, Fumihiro; ; Inoue, Osamu*; Hara, Toshiharu*

JAERI-M 93-024, 31 Pages, 1993/02

JAERI-M-93-024.pdf:0.84MB

no abstracts in English

JAEA Reports

Speedup of MCACE, a Monte Carlo code for evaluation of shielding safety, by parallel computer,(1); Paralleling of MCACE code and performance evaluation by simulator

*; ; Masukawa, Fumihiro; Naito, Yoshitaka; Minami, Kazuyoshi*

JAERI-M 91-066, 77 Pages, 1991/04

JAERI-M-91-066.pdf:1.82MB

no abstracts in English

35 (Records 1-20 displayed on this page)