Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Measurement and analysis of reactivity worth of $$^{241}$$Am sample in water-moderated low-enriched UO$$_2$$ fuel lattices at TCA

Sakurai, Takeshi; Mori, Takamasa; Suzaki, Takenori*; Okajima, Shigeaki; Ando, Yoshihira*; Yamamoto, Toru*; Liem, P. H.*

Journal of Nuclear Science and Technology, 48(5), p.816 - 825, 2011/05

 Times Cited Count:2 Percentile:18.37(Nuclear Science & Technology)

Journal Articles

Research activities of Japan Nuclear Data Committee in fiscal years of 2003 and 2004

Igashira, Masayuki*; Watanabe, Yukinobu*; Fukahori, Tokio; Okumura, Keisuke; Katakura, Junichi; Chiba, Satoshi; Shibata, Keiichi; Yamano, Naoki*; Nakagawa, Tsuneo; Odano, Naoteru*; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 6(1), p.85 - 96, 2007/03

This technical note summarizes research activities on nuclear data carried out by Japanese Nuclear Data Committee (JNDC) during the fiscal years of 2003 and 2004. During this period, the nuclear data files for special purposes (JENDL-HE-2004 and JENDL-PD-2004) were released. Other activities are described: analysis of post nuclear fuel irradiation experiments, nuclear chart and nuclear data evaluation for astrophysics.

JAEA Reports

Study on the prediction accuracy of nuclide generation and depletion with JENDL

Okumura, Keisuke; Oki, Shigeo*; Yamamoto, Munenari*; Matsumoto, Hideki*; Ando, Yoshihira*; Tsujimoto, Kazufumi; Sasahara, Akihiro*; Katakura, Junichi; Matsumura, Tetsuo*; Aoyama, Takafumi*; et al.

JAERI-Research 2004-025, 154 Pages, 2005/01

JAERI-Research-2004-025.pdf:19.46MB

This report summarizes the activity (FY2000-2003) of Working Group (WG) on Evaluation of Nuclide Generation and Depletion under Subcommittee on Nuclear Fuel Cycle of Japanese Nuclear Data Committee. In the WG, analyses of Post Irradiation Examinations have been carried out for UO$$_{2}$$ and MOX fuels irradiated in PWRs, BWRs and FBRs, and for actinide samples irradiated in fast reactors, by using ORIGEN or more detailed calculation codes with their libraries based on JENDL-3.2, JENDL-3.3 and other foreign nuclear data files. From these results, current prediction accuracy and problems for evaluation of nuclide generation and depletion are discussed. Furthermore, this report covers other products of our activity; development of the ORIGEN libraries for PWR, BWR and FBR based on JENDL-3.3, study on introduction of neutron spectrum index to ORIGEN calculations, and results of questionnaire survey on desirable accuracy of ORIGEN calculations.

Journal Articles

Estimation of spent fuel compositions from light water reactors

Ando, Yoshihira*; Nishihara, Kenji; Takano, Hideki

Journal of Nuclear Science and Technology, 37(10), p.924 - 933, 2000/10

no abstracts in English

JAEA Reports

OECD/NEA burnup credit criticality benchmarks phase IIIA; Criticality calculations of BWR spent fuel assemblies in storage and transport

Okuno, Hiroshi; Naito, Yoshitaka*; Ando, Yoshihira*

JAERI-Research 2000-041, 179 Pages, 2000/09

JAERI-Research-2000-041.pdf:6.11MB

no abstracts in English

JAEA Reports

Mass balance of MA accumulation and transmutation in double strata transmutation system

Nishihara, Kenji; Ando, Yoshihira*; Takano, Hideki

JAERI-Research 99-074, p.24 - 0, 2000/01

JAERI-Research-99-074.pdf:1.05MB

no abstracts in English

JAEA Reports

Estimation of LWR spent fuel composition

Ando, Yoshihira*; Takano, Hideki

JAERI-Research 99-004, 270 Pages, 1999/02

JAERI-Research-99-004.pdf:21.43MB

no abstracts in English

Journal Articles

International studies on burnup credit criticality safety by an OECD/NEA working group, 2; Calculation benchmarks for BWR spent fuels

; *; Suyama, Kenya; Ando, Yoshihira*

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 2, p.566 - 575, 1999/00

no abstracts in English

Oral presentation

Am-241 sample reactivity experiments in TCA, 1; Measurement results and evaluation of uncertainty in calculation caused by nuclear data uncertainty

Sakurai, Takeshi; Mori, Takamasa; Suzaki, Takenori*; Okajima, Shigeaki; Ando, Yoshihira*; Yamamoto, Toru*

no journal, , 

Measurement and analysis have been made for the reactivity worth of Am-241 oxide sample(23 g) in water-moderated low-enriched UO$$_{2}$$ fuel lattices with water-to-fuel volume ratios ranging from 0.56 to 3.0 at TCA of JAEA to validate the capture cross section of Am-241 of thermal to resonance energy region in current nuclear data library. The reactivity worth of sample at the core center was measured with uncertainty of 0.4% $$sim$$ 2.1%. The analysis was made by using the continuous energy Monte Carlo transport code MVP with JENDL-3.3 nuclear data. The reactivity worth was calculated from difference of effective multiplication factors and was obtained with statistical uncertainties of 0.6% $$sim$$ 1.1%. The calculation underestimated the measurement by 4% $$sim$$ 9%. Furthermore, an evaluation was made for the uncertainty in calculation caused by nuclear data uncertainty to investigate the present discrepancy between calculation and measurement.

Oral presentation

Am-241 sample reactivity experiments in TCA, 2; Analysis of experimental cores and sensitivity analysis on Am-241 cross sections

Ando, Yoshihira*; Yamamoto, Toru*; Sakurai, Takeshi; Okajima, Shigeaki; Mori, Takamasa; Liem, P. H.*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of Doppler reactivity effect in MOX fueled LWR using FCA. 1; Scope of experiments and results in a uranium fueled core

Ando, Masaki; Fukushima, Masahiro; Okajima, Shigeaki; Yamamoto, Toru*; Ando, Yoshihira*

no journal, , 

Evaluation of the Doppler reactivity effect of MOX fueled LWR is planned and being carried out using FCA. In this presentation, the scope of the plan is introduced, and the results of the first experiment using uranium samples in a uranium fueled core and the analysis is reported. The result of the analysis using the JENDL-3.3 library and FCA's code system showed good agreement with the measured values.

Oral presentation

Evaluation of Doppler reactivity effect in MOX fueled LWR using FCA, 2; Analysis of experimental data of UO$$_{2}$$ samples in a uranium fueled core

Suzuki, Motomu*; Yamamoto, Toru*; Ando, Yoshihira*; Nakajima, Tetsuo*; Ando, Masaki; Kugo, Teruhiko; Okajima, Shigeaki

no journal, , 

To obtain experimental data to evaluate calculation accuracy for the Doppler effect in MOX fueled LWR, a series of experiment has been carried out at FCA with the use of uranium and plutonium samples. Parametric survey calculations as for the modeling, nuclear data library and calculation method were carried out for the experiments in the uranium core using uranium samples. The effect of those parameters for the calculation of the Doppler effect was obtained.

12 (Records 1-12 displayed on this page)
  • 1