Effect of experiments using Transmutation Physics Experimental Facility on the reduction of uncertainties in reactor physics parameters of an accelerator-driven system

Iwamoto, Hiroki; Nishihara, Kenji; Katano, Ryota*; Fukushima, Masahiro; Tsujimoto, Kazufumi

JAEA-Research 2014-033, 82 Pages, 2015/03

JAEA-Research-2014-033.pdf:6.53MB

The effect of experiments using Transmutation Physics Experimental Facility (TEF-P) is analysed from the viewpoint of the reduction of uncertainties in reactor physics parameters (criticality and coolant void reactivity) of an accelerator-driven system (ADS). The analysis is conducted by the nuclear-data adjustment method using JENDL-4.0 on the assumption that ve types of reactor physics experiments (a total of 44 experiments) are performed in TEF-P: (1) criticality experiment, (2) lead void reactivity experiment, (3) reaction rate ratio experiment, (4) sample reactivity experiment, and (5) fuel replacement reactivity experiment. As the result, 1.0% of uncertainty in criticality is found to be reduced to approximately 0.4%, and effective experiments for the reduction of uncertainty in criticality and coolant void reactivity are shown to be fuel replacement reactivity experiments and lead void reactivity experiments, respectively. Although these effects depend largely on the composition and amount of minor-actinide (MA) fuels, it is found that a combination of different types of experiments and database of existing experiments is effective in reducing the uncertainties.

ComparaUve analyses on nuclear charaderistics of water-cooled breeder cores

; Sato, Wakaei*;

JNC TN9400 2000-037, 87 Pages, 2000/03

JNC-TN9400-2000-037.pdf:3.48MB

ln order to compare the nuclear characteristics of water-cooled bleeder cores with that of LMFBR, MOX fuel cell models are established for boiling and non-boiling LWR, non-boiling HWR and sodium-cooled reactor. Frst, the comarison is made between the heterogeneous cell calculation results by SRAC and those by SLAROM. The results show some differences as for neutron energy spectrum, one-grouped cross section and conversion ratio due to the different grouped cross section library (both are based on JENDL-3.2, though) used for each code, however, the difference is acceptably small for grasping the basic characteristics of the above-mentioned cores. Second, using the SLAROM code, main core parameters such as mean neutron energy, ratio of fast neutron and -value, are analyzed. The comparison between the cores show that softened neutron spectrum by the scattering effect of hydrogen or heavy hydrogen increase the contribution of nuclear reaction (especially for neutron capture reaction rather than fission reaction) in lower energy region comparing with LMFBR. ln order to overcome the effect, tighter lattice than LMFBR is necessary for water-cooled cores to realize the breeding of fissile nuclides. Third, effects of Pu isotopic composition on the breeding ratio are evaluated using SRAC burnup calculation. From the results, it is confirmed that degraded Pu (larger ratio of Pu-240) show the larger breeding ratio. At last, sensitivity analyses are made for k-effective and main reaction ratios. As for k-effective, using a temporary covariance data of JENDL-3.2, uncertainty resulting from the cross sections' error is analyzed for a boiling LWR and a sodium-cooled reactor. The boiling LWR core shows larger sensitivity in lower energy region than the sodium-cooled reactor (especially for the energy region lower than 1kev), And, 18-group analysis that is considered acceptably good for LMFBR analysis, should not be enough for accurate sensitivity estimation of ...

Evaluation of covariance for fission neutron spectra

Kawano, Toshihiko*; Osawa, Takaaki*; Shibata, Keiichi; *

JAERI-Research 99-009, 43 Pages, 1999/02

JAERI-Research-99-009.pdf:1.36MB

no abstracts in English

Evaluation of covariance data for chromium, iron and nickel contained in JENDL-3.2

S.Oh*; Shibata, Keiichi

Journal of Nuclear Science and Technology, 35(1), p.66 - 75, 1998/01

https://doi.org/10.3327/jnst.35.66

no abstracts in English

JENDL-3.2 covariance file for fast reactors

Shibata, Keiichi; Chiba, Satoshi; Fukahori, Tokio; Hasegawa, Akira; Iwamoto, Osamu; *; *; Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; et al.

Proc. of Int. Conf. on Nucl. Data for Science and Technol., p.904 - 906, 1997/00

no abstracts in English

Uncertainties in evaluated total cross-section data for 14 nuclides contained in JENDL-3.2

Nakamua, Masahiro*; Shibata, Keiichi

JAERI-Research 95-068, 51 Pages, 1995/10

JAERI-Research-95-068.pdf:1.38MB

no abstracts in English

Proceedings of the Specialists Meeting on Covariance Data; July 1516, 1993, Tokai, Japan

Nakajima, Yutaka

JAERI-M 94-068, 89 Pages, 1994/03

JAERI-M-94-068.pdf:2.52MB

no abstracts in English

Study of relationship between MUF correlation and detection sensitivity of statistical analysis

; Ihara, Hitoshi; Yamamoto, Yoichi; Ikawa, Koji

JAERI-M 89-171, 152 Pages, 1989/11

JAERI-M-89-171.pdf:4.1MB

no abstracts in English

The Calculation of Efficiency of Li-Glass and B-NaI Detectors by the Program ELIS

;

JAERI-M 82-193, 56 Pages, 1982/12

JAERI-M-82-193.pdf:1.32MB

no abstracts in English

How to use nuclear data covariance 2015

Ishikawa, Makoto

no journal, , 

As a topic of Nuclear-data Tutorial, the author will make a lecture on the method to use nuclear-data covariance, which includes the background of nuclear-data covariance use, the physical meaning of covariance, the method to evaluate the prediction accuracy of nuclear core-parameters with covariance, and how to improve the nuclear design accuracy with covariance.