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Journal Articles

Benchmark tests of newly-evaluated data of $$^{235}$$U for CIELO project using integral experiments of uranium-fueled FCA assemblies

Fukushima, Masahiro; Kitamura, Yasunori*; Yokoyama, Kenji; Iwamoto, Osamu; Nagaya, Yasunobu; Leal, L. C.*

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.605 - 619, 2016/05

A nuclear data of $$^{235}$$U has been recently evaluated for the CIELO (Collaborative International Evaluated Library Organization) project. We tested the newly-evaluated data of $$^{235}$$U using integral experiments of the Fast Critical Assembly (FCA) performed at JAEA. We selected two integral data of uranium-fueled FCA assemblies; one is the sodium-void reactivity worth of FCA XXVII-1 assembly and the other is the criticalities of the seven assemblies of FCA IX. The benchmark tests support the evaluation done in the resonance regions. However, the $$^{235}$$U capture cross section above the unresolved resonance range needs further investigation.

JAEA Reports

Evaluation of covariances for resolved resonance parameters of $$^{235}$$U, $$^{238}$$U, and $$^{239}$$Pu in JENDL-3.2

Kawano, Toshihiko*; Shibata, Keiichi

JAERI-Research 2003-001, 36 Pages, 2003/02

JAERI-Research-2003-001.pdf:1.67MB

Evaluation of covariances for resolved resonance parameters of $$^{235}U$$, $$^{238}U$$, and $$^{239}Pu$$ was carried out. Although a large number of resolved resonances are observed for major actinides, uncertainties in averaged cross sections are more important than those in resonance parameters in reactor calculations. We developed a simple method which is to provide a covariance matrix for the resolved resonance parameters on the basis of uncertainties in the averaged cross sections. The method was adopted to evaluate the covariance data for some important actinides, and the results were compiled in the JENDL-3.2 covariance file.

JAEA Reports

Neutron and proton nuclear data evaluation for $$^{235}$$U and $$^{238}$$U at energies up to 250 MeV

Konobeyev, A. Y.; Fukahori, Tokio; Iwamoto, Osamu

JAERI-Research 2002-028, 69 Pages, 2002/12

JAERI-Research-2002-028.pdf:1.93MB

Basic features of nuclear data evaluation for uranium isotopes $$^{235}$$U and 238U at intermediate energies are described. The coupled channel optical model was used to obtain total cross section, reaction cross section, angular distributions and transmission coefficients. The direct, pre-compound and evaporation models were used to describe neutron and charged particles emission from excited nuclei. The neutron data evaluated were combined with JENDL-3.3 data below 20 MeV to obtain a full data set in the whole energy range between 10$$^{-5}$$ eV and 250 MeV. Evaluation of the proton data has been done at energies from 1 to 250 MeV

Journal Articles

Uncertainty analyses in the resolved resonance region of $$^{235}U$$, $$^{238}U$$, and $$^{239}Pu$$ with the Reich-Moore $$R$$-matrix theory for JENDL-3.2

Kawano, Toshihiko*; Shibata, Keiichi

Journal of Nuclear Science and Technology, 39(8), p.807 - 815, 2002/08

 Times Cited Count:5 Percentile:61.7(Nuclear Science & Technology)

A simple method to estimate covariances for resolved resonance parameters was developed. Although a large number of resolved resonances are observed for major actinides, uncertainties in averaged cross sections are more important than those in resonance parameters in reactor calculations. The method developed here is to derive a covariance matrix for the resolved resonance parameters which gives an appropriate uncertainty of the averaged cross sections. The method was adopted to evaluate the covariance data for $$^{235}U$$, $$^{238}U$$, and $$^{239}Pu$$ resonance parameters in JENDL-3.2,with the Reich-Moore R-matrix formula.

JAEA Reports

Comparison of $$^{235}$$U fission cross sections in JENDL-3.3 and ENDF/B-VI

Kawano, Toshihiko*; Carlson, A. D.*; Matsunobu, Hiroyuki*; Nakagawa, Tsuneo; Shibata, Keiichi; Talou, P.*; Young, P. G.*; Chadwick, M. B.*

JAERI-Research 2001-058, 28 Pages, 2002/01

JAERI-Research-2001-058.pdf:1.71MB

no abstracts in English

Journal Articles

Status of international benchmark experiment for effective delayed neutron fraction ($$beta$$$$_{eff}$$)

Okajima, Shigeaki; Sakurai, Takeshi; Mukaiyama, Takehiko

JAERI-Conf 97-005, 00(00), p.71 - 76, 1997/00

no abstracts in English

Journal Articles

Comments on JENDL-3.2 delayed neutron data

Okajima, Shigeaki

Kaku Deta Nyusu (Internet), 0(56), p.190 - 193, 1997/00

no abstracts in English

JAEA Reports

Sensitivity analysis of JENDL-3.2 based on benchmark calculations for fast reactors

Z.Pintai*; Takano, Hideki

JAERI-Research 96-010, 72 Pages, 1996/03

JAERI-Research-96-010.pdf:2.01MB

no abstracts in English

Journal Articles

Measurements of the number of neutrons emitted per fission in a fast neutron spectrum for $$^{235}$$U,$$^{237}$$Np, and $$^{243}$$Am

H.H.Saleh*; T.A.Parish*; W.H.Miller*; Oigawa, Hiroyuki; S.Raman*

Nuclear Instruments and Methods in Physics Research B, 103, p.393 - 400, 1995/00

 Times Cited Count:1 Percentile:75.3

no abstracts in English

Journal Articles

JENDL-3 revision 2 - Its evaluation and validation

; Takano, Hideki; Nakagawa, Tsuneo

Transactions of the American Nuclear Society, 73, p.424 - 425, 1995/00

no abstracts in English

Journal Articles

Measurements and analyses of the ratio of $$^{238}$$U captures to $$^{235}$$U fission in low-enriched UO$$_{2}$$ tight lattices

Nakajima, Ken; ; Yamamoto, Toshihiro; ; Suzaki, Takenori

Journal of Nuclear Science and Technology, 31(11), p.1160 - 1170, 1994/11

 Times Cited Count:7 Percentile:41.09(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Report on the first version of Japnese evaluated nuclear data library; JENDL-1

; Kikuchi, Yasuyuki; Nakagawa, Tsuneo

Nippon Genshiryoku Gakkai-Shi, 20(1), p.30 - 36, 1978/01

 Times Cited Count:0

no abstracts in English

Journal Articles

Effect of nonelastic neutron anisotropy on fission rates measured in a graphite-reflected lithium assembly

; D.W.Muir*;

Journal of Nuclear Science and Technology, 14(9), p.680 - 681, 1977/09

 Times Cited Count:10

no abstracts in English

Journal Articles

A Large area thin NaI(Tl) detector for external counting of low-energy emitters in lung

Journal of Nuclear Science and Technology, 12(7), p.442 - 449, 1975/07

 Times Cited Count:1

no abstracts in English

Journal Articles

Revision of JAERI-Fast Set based on benchmark test

; ; Katsuragi, Satoru

Dai-1-Kai Toropikaru Mithingu Hobunshu; Kosokuro Butsuri, p.68 - 76, 1973/00

no abstracts in English

Journal Articles

The Spectrochemical Determination of U-235

;

Bunko Kenkyu, 19(1), p.38 - 42, 1970/00

no abstracts in English

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