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Journal Articles

Corrections to the $$^{148}$$Nd method of evaluation of burnup for the PIE samples from Mihama-3 and Genkai-1 reactors

Suyama, Kenya; Mochizuki, Hiroki*

Annals of Nuclear Energy, 33(4), p.335 - 342, 2006/03

 Times Cited Count:8 Percentile:52.29(Nuclear Science & Technology)

The value of the burnup is one of the most important parameters of samples taken by post irradiation examination (PIE). In this study, concerning the PIE data from Mihama-3 and Genkai-1 PWRs, which were taken at the Japan Atomic Energy Research Institute, the burnup values of the PIE samples were re-evaluated and the PIE data are re-analyzed using SWAT and SWAT2 code systems with JENDL-3.3 library. This analysis concludes that the burnup values of samples from Mihama-3 and Genkai-1 PWRs should be corrected of 2-3%. The effect of re-evaluation of the burnup value on the neutron multiplication factor is approximately 1% for PIE samples having the burnup of larger than 30 GWd/t. Comparison between calculation results using a single pin cell model and an assembly model is carried out. Because the both results agreed within a few percents, we concluded that the single pin cell model is suitable for the analysis of PIE samples and the underestimation of plutonium isotopes does not result from the geometry model.

Journal Articles

Validation of minor actinide cross sections by studying samples irradiated for 492 days at the dounreay prototype fast reactor, 2; Burnup calculations

Tsujimoto, Kazufumi; Kono, Nobuaki; Shinohara, Nobuo; Sakurai, Takeshi; Nakahara, Yoshinori; Mukaiyama, Takehiko; Raman, S.*

Nuclear Science and Engineering, 144(2), p.129 - 141, 2003/06

To evaluate neutron cross-section data of minor actinides, separated actinide samples and dosimetry samples were irradiated at the Dounreay Prototype Fast Reactor for 492 effective full power days. Based on the burnup calculations of major actinide and dosimetry samples, the neutron flux distribution and the flux level were adjusted at the locations where minor actinide samples were irradiated. The burnup calculations were carried out for minor actinides using the determined flux distribution and flux level. This paper discusses the burnup calculations and the validation of minor actinide cross-section data in evaluated nuclear data libraries. We find that we can obtain reliable FIMA (fission per initial metallic atom) values by using the $$^{148}$$Nd method except that the uncertainties in the FIMA values are large for $$^{234}$$U, $$^{238}$$Pu, Am isotopes, and Cm isotopes because the $$^{148}$$Nd yields are known poorly for these isotopes and are probably overestimated. For these isotopes, measurements to improve the fission-yield data are needed. We also find that, in general, the JENDL-3.2 nuclear data for the minor actinides are adequate for the conceptual design study of transmutation systems. But, there are some nuclides (especially $$^{238}$$Pu and $$^{242}$$Pu) for which new measurements are needed particulary if the minor actinides constitute a major part of the nuclear fuel.

Journal Articles

Validation of minor actinide cross sections by studying samples irradiated for 492 days at the dounreay prototype fast reactor, 2; Burnup calculations

Tsujimoto, Kazufumi; Kono, Nobuaki; Shinohara, Nobuo; Sakurai, Takeshi; Nakahara, Yoshinori; Mukaiyama, Takehiko*; Raman, S.*

Nuclear Science and Engineering, 144(2), p.129 - 141, 2003/06

 Times Cited Count:10 Percentile:58.26(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Systematics of fission product mass yields with 5 gaussian functions

Katakura, Junichi

JAERI-Research 2003-004, 19 Pages, 2003/03

JAERI-Research-2003-004.pdf:0.76MB

no abstracts in English

Journal Articles

Photofission of $$^{209}$$Bi at intermediate energies

Haba, Hiromitsu; Kasaoka, Makoto*; Igarashi, Manabu*; Washiyama, Koshin*; Matsumura, Hiroshi*; Oura, Yasuji*; Shibata, Seiichi*; Sakamoto, Ko*; Furukawa, Michiaki*; Fujiwara, Ichiro*

Radiochimica Acta, 90(7), p.371 - 382, 2002/08

 Times Cited Count:2 Percentile:17.59(Chemistry, Inorganic & Nuclear)

The reaction yields of 63 radionuclides with the mass number A = 56-135 produced in the photofission of $$^{209}$$Bi by bremsstrahlung of end-point energies (E$$_{0}$$) from 450 to 1100 MeV have been measured using a catcher foil technique. The charge distribution was well reproduced by a Gaussian function with the most probable charge (Z$$_{p}$$) expressed by Z$$_{p}$$ = RA + S, and with the A-independent FWHME$$_{CD}$$. The charge distribution parameters R, S and FWHM$$_{CD}$$ were independent of E$$_{0}$$ above 600 MeV. The weighted mean values at E$$_{0}$$ $$geq$$ 600 MeV were R = 0.421 $$pm$$ 0.001, S = 0.6 $$pm$$ 0.1 and FWHM$$_{CD}$$ = 2.1 $$pm$$ 0.1 charge unit (c.u.). Based on the charge distribution parameters, the symmetric mass yield distributions with the most probable mass A$$_{p}$$ of 96 $$pm$$ 1 mass unit (m.u.) and the width FWHM$$_{MD}$$ of 33 $$pm$$ 1 m.u. were also obtained. The characteristics of the charge and mass yield distributions are discussed by referring to those for $$^{197}$$Au based on the results of calculations using PICA3/GEM.

JAEA Reports

Design of ex-vessel neutron monitor for ITER

Nishitani, Takeo; Iguchi, Tetsuo*; Ebisawa, Katsuyuki*; Yamauchi, Michinori*; Walker, C.*; Kasai, Satoshi

JAERI-Tech 2002-062, 39 Pages, 2002/07

JAERI-Tech-2002-062.pdf:1.65MB

no abstracts in English

JAEA Reports

Technical feasibility study for the D-T neutron monitor using activation of flowing water

Uno, Yoshitomo; Kaneko, Junichi; Nishitani, Takeo; Maekawa, Fujio; Tanaka, Teruya; Ikeda, Yujiro; Takeuchi, Hiroshi

JAERI-Research 2001-007, 42 Pages, 2001/03

JAERI-Research-2001-007.pdf:8.74MB

no abstracts in English

JAEA Reports

DCHAIN-SP 2001: High energy particle induced radioactivity calculation code

Kai, Tetsuya; Maekawa, Fujio; Kosako, Kazuaki*; Kasugai, Yoshimi; Takada, Hiroshi; Ikeda, Yujiro

JAERI-Data/Code 2001-016, 82 Pages, 2001/03

JAERI-Data-Code-2001-016.pdf:4.22MB

no abstracts in English

Journal Articles

Isomeric yield ratios of $$^{134}$$I and $$^{136}$$I in the proton-, $$^{12}$$C- and $$^{19}$$F-induced fission of $$^{235}$$U, $$^{237}$$Np and $$^{238}$$U

Shinohara, Nobuo; Tsukada, Kazuaki; Ichikawa, Shinichi; Magara, Masaaki; Hatsukawa, Yuichi

Radiochimica Acta, 88(1), p.1 - 5, 2000/00

 Times Cited Count:1 Percentile:12.53(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Report of the first research coordinate meeting for IAEA/CRP on fission product yield data required for transmutation of minor actinide nuclear waste

Fukahori, Tokio; Katakura, Junichi

Nihon Genshiryoku Gakkai-Shi, 40(5), p.363 - 366, 1998/00

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

no abstracts in English

Journal Articles

Design of ITER neutron yield monitor using microfission chambers

Nishitani, Takeo; Ebisawa, Katsuyuki*; Iguchi, Tetsuo*; Matoba, Toru

Fusion Engineering and Design, 34-35, p.567 - 571, 1997/00

 Times Cited Count:12 Percentile:69.34(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Cumulative yields of short-lived Ru isotopes in the $$^{12}$$C- and $$^{19}$$F-induced fission of $$^{233}$$U, $$^{235}$$U, $$^{238}$$U and $$^{237}$$Np

Shinohara, Nobuo; Tsukada, Kazuaki; ; ; Otsuki, Tsutomu*

Radiochimica Acta, 68, p.21 - 26, 1995/00

no abstracts in English

Journal Articles

Absolute calibration of the JT-60U neutron monitors using a $$^{252}$$Cf neutron source

Nishitani, Takeo; Takeuchi, Hiroshi; Kondoh, Takashi; Ito, Takao*; Kuriyama, Masaaki; Ikeda, Yujiro; Iguchi, Tetsuo*; Barnes, C. W.*

Review of Scientific Instruments, 63(11), p.5270 - 5278, 1992/11

 Times Cited Count:72 Percentile:97.17(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Analysis of uncertainties in summation calculations of decay heat using JNDC FP nuclear data library

Katakura, Junichi; Iijima, Shungo*

Journal of Nuclear Science and Technology, 29(1), p.11 - 23, 1992/01

no abstracts in English

JAEA Reports

Absolute calibration of the neutron yield measurement on JT-60 Upgrade

Nishitani, Takeo; Takeuchi, Hiroshi; Barnes, C. W.*; Iguchi, Tetsuo*; Nagashima, Akira; Kondoh, Takashi; Sakasai, Akira; Itami, Kiyoshi; Tobita, Kenji; Nagashima, Keisuke; et al.

JAERI-M 91-176, 23 Pages, 1991/10

JAERI-M-91-176.pdf:1.08MB

no abstracts in English

JAEA Reports

JAEA Reports

Neutron Yield Monitors for the Fusion Neutronics Source(FNS); For 80$$^{circ}$$Beam Line

; ; ; ;

JAERI-M 83-219, 28 Pages, 1983/12

JAERI-M-83-219.pdf:1.03MB

no abstracts in English

JAEA Reports

JNDC nuclear data library of fission products

Tasaka, Kanji; ; *; ; ; *

JAERI 1287, 218 Pages, 1983/10

JAERI-1287.pdf:11.61MB

no abstracts in English

JAEA Reports

PROFPY: A Computer Code for Producing Nuclear Data Library of Fission Products

; ; Tasaka, Kanji; *; *; *

JAERI-M 9714, 132 Pages, 1981/10

JAERI-M-9714.pdf:3.58MB

no abstracts in English

JAEA Reports

JNDC FP Decay and Yield Data

; ; Tasaka, Kanji; *; *; *

JAERI-M 9715, 117 Pages, 1981/09

JAERI-M-9715.pdf:4.54MB

no abstracts in English

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