JOPSS - Search Results

; Nakao, Noriaki*; Tanaka, Shunichi; Nakamura, Takashi*; Shin, Kazuo*; Tanaka, Susumu; Takada, Hiroshi; Meigo, Shinichiro; Nakane, Yoshihiro; Sakamoto, Yukio; et al.

Nuclear Science and Engineering, 124(2), p.243 - 257, 1996/00

https://doi.org/10.13182/NSE96-A28575

Times Cited Count：41 Percentile：94.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

The Vector and parallel processing of MORSE code on Monte Carlo machine

*; Higuchi, Kenji

JAERI-Tech 95-051, 59 Pages, 1995/11

JAERI-Tech-95-051.pdf:1.95MB

no abstracts in English

Journal Articles

Neutronics integral experiments of lithium-oxide fusion blanket with heterogeneous configurations using deuterium-tritium neutrons

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; ; ; Kosako, Kazuaki*; Maekawa, Hiroshi; Nakakawa, Masayuki; Mori, Takamasa; Nakamura, Tomoo; et al.

Fusion Technology, 28(1), p.216 - 235, 1995/08

no abstracts in English

Journal Articles

Dose conversion coefficients for external photons based on ICRP 1990 recommendations

Yamaguchi, Yasuhiro

Journal of Nuclear Science and Technology, 31(7), p.716 - 725, 1994/07

https://doi.org/10.3327/jnst.31.716

Times Cited Count：6 Percentile：52.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Shielding experiments with quasi-monoenergetic neutrons between 15 and 90 MeV at 90 MV AVF cyclotron facility TIARA

Sakamoto, Yukio; ; Nakane, Yoshihiro; Tanaka, Shunichi; Tanaka, Susumu; Nakamura, Takashi*; Baba, Mamoru*; *; Shin, Kazuo*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.809 - 815, 1994/00

no abstracts in English

Journal Articles

Absolute measurements of activation cross sections of $^{27}$ Al(n,p) $^{27}$ Mg, $^{27}$ Al(n,) $^{24}$ Na, $^{56}$ Fe(n,p) $^{56}$ Mn, $^{90}$ Zr(n,2n) $^{89m+g}$ Zr and $^{93}$ Nb(n,2n) $^{92m}$ Nb at energy range of 13.314.9MeV

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

Journal of Nuclear Science and Technology, 30(9), p.870 - 880, 1993/09

https://doi.org/10.3327/jnst.30.870

Times Cited Count：22 Percentile：86.8(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

https://doi.org/10.3327/jnst.30.926

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

no abstracts in English

Journal Articles

Development of a common nuclear group constants library system; JSSTDL-295n-104 based on JENDL-3 nuclear data library

Nuclear Data for Science and Technology, p.232 - 234, 1992/00

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

JAEA Reports

DEEP code to calculate dose equivalents in human phantom for external photon exposure by Monte Carlo method

Yamaguchi, Yasuhiro

JAERI-M 90-235, 69 Pages, 1991/01

JAERI-M-90-235.pdf:1.75MB

no abstracts in English

JAEA Reports

INTERF; The Reaction rates and spectra editing code for analysis of fusion neutronics experiments

Kosako, Kazuaki*

JAERI-M 90-199, 114 Pages, 1990/11

JAERI-M-90-199.pdf:2.79MB

no abstracts in English

JAEA Reports

Vectorization of Morse-DD Code

; *;

JAERI-M 87-032, 49 Pages, 1987/02

JAERI-M-87-032.pdf:1.26MB

no abstracts in English

Journal Articles

Measurement and analysis of an angular neutron flux on a beryllium slab irradiated with deuterium-tritium neutrons

;

Nuclear Science and Engineering, 97, p.220 - 234, 1987/00

https://doi.org/10.13182/NSE87-A23504

Times Cited Count：24 Percentile：88.58(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Shielding Analyses for Design of the Upgraded JRR-3 Research Reactor・3 ; Physics and Shielding of Neutron Guides

; ; ; ; ; ; *; *

JAERI-M 86-028, 107 Pages, 1986/03

JAERI-M-86-028.pdf:2.94MB

no abstracts in English

Journal Articles

Neutron field characteristics in concrete cavity having a D-T neutron source

; ; ; Nakagawa, Masayuki;

Transactions of the American Nuclear Society, 52, p.112 - 113, 1986/00

no abstracts in English

JAEA Reports

Shielding Analyses for Design of the Upgraded JRR-3 Research Reactor・2-Shielding of Neutron Beam Holes-

; ; ; ; ; *

JAERI-M 85-105, 113 Pages, 1985/07

JAERI-M-85-105.pdf:2.56MB

no abstracts in English

JAEA Reports

MORSE-DD:A Monte Carlo Code Using Multi-group Double Differential Form Cross Sections

Nakagawa, Masayuki;

JAERI-M 84-126, 74 Pages, 1984/07

JAERI-M-84-126.pdf:1.38MB

no abstracts in English

Presentation/Publication Type

Journal/Book Title

Meeting title

First Author

Keyword

Language

Publication Year

Held year of conference

A Note on the basis set approach in the constrained interpolation profile method

Study on dose distributions in a slab phantom irradiated by several tens MeV neutrons

Difficulties in vector-parallel processing of Monte Carlo codes

Transmission through shields of quasi-monoenergetic neutrons generated by 43- and 68-MeV protons,II; Iron shielding experiment and analysis for investigating calculational method and cross-section data

The Vector and parallel processing of MORSE code on Monte Carlo machine

Neutronics integral experiments of lithium-oxide fusion blanket with heterogeneous configurations using deuterium-tritium neutrons

Dose conversion coefficients for external photons based on ICRP 1990 recommendations

Shielding experiments with quasi-monoenergetic neutrons between 15 and 90 MeV at 90 MV AVF cyclotron facility TIARA

Absolute measurements of activation cross sections of $^{27}$ Al(n,p) $^{27}$ Mg, $^{27}$ Al(n,) $^{24}$ Na, $^{56}$ Fe(n,p) $^{56}$ Mn, $^{90}$ Zr(n,2n) $^{89m+g}$ Zr and $^{93}$ Nb(n,2n) $^{92m}$ Nb at energy range of 13.314.9MeV

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

Development of a common nuclear group constants library system; JSSTDL-295n-104 based on JENDL-3 nuclear data library

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

DEEP code to calculate dose equivalents in human phantom for external photon exposure by Monte Carlo method

INTERF; The Reaction rates and spectra editing code for analysis of fusion neutronics experiments

Vectorization of Morse-DD Code

Measurement and analysis of an angular neutron flux on a beryllium slab irradiated with deuterium-tritium neutrons

Shielding Analyses for Design of the Upgraded JRR-3 Research Reactor・3 ; Physics and Shielding of Neutron Guides

Neutron field characteristics in concrete cavity having a D-T neutron source

Shielding Analyses for Design of the Upgraded JRR-3 Research Reactor・2-Shielding of Neutron Beam Holes-

MORSE-DD:A Monte Carlo Code Using Multi-group Double Differential Form Cross Sections