Measurement and analysis of reactivity worth of Am sample in water-moderated low-enriched UO 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

https://doi.org/10.3327/jnst.48.816

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 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.

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

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

Evaluation of Doppler reactivity effect in MOX fueled LWR using FCA, 2; Analysis of experimental data of UO 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.

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 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% 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% 1.1%. The calculation underestimated the measurement by 4% 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.