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Journal Articles

Direct neutron spectrum measurement to validate $$^{rm nat}$$Zr(n,2n) reaction cross-section at 14 MeV

Murata, Isao*; Shiken, Kimiaki*; Kondo, Keitaro; Matsunaka, Masayuki*; Ota, Masayuki*; Miyamaru, Hiroyuki*; Ochiai, Kentaro; Konno, Chikara; Nishitani, Takeo

Fusion Engineering and Design, 84(7-11), p.1376 - 1379, 2009/06

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

Lithium zirconate, Li$$_{2}$$ZrO$$_{3}$$, is known as a candidate blanket material in a fusion reactor. According to the independent benchmark studies for zirconium by JAERI, Kyoto University and Osaka University, the neutron spectrum calculations show fairly large overestimation for most evaluated nuclear data libraries. The author's group expects that the overestimation be due to a problem of evaluation for the (n,2n) reaction, because the (n,2n) reaction cross section is not well determined experimentally. In the present study, two neutrons emitted from $$^{rm nat}$$Zr(n,2n) reaction have been measured directly to reveal the problem. As a result of measurements, the cross section obtained for energies above 1 MeV, which is the lower measurable limit energy, shows a little larger than JENDL-3.3. This is an opposite result to the benchmark analysis. However, an extrapolation for the low energy region by the evaporation spectrum with the nuclear temperature of 1 MeV brought the smaller total (n,2n) reaction cross section than JENDL-3.3, which is comparable to ENDF/B-VI. This result suggests that the discrepancies reported previously might be due to inappropriate evaluation of nuclear temperature.

Journal Articles

Preliminary spectrum shifter design for intermediate energy nuclear data benchmark experiments with DT neutrons

Ota, Masayuki*; Kondo, Keitaro; Matsunaka, Masayuki*; Miyamaru, Hiroyuki*; Murata, Isao*; Iida, Toshiyuki*; Ochiai, Kentaro; Konno, Chikara

Fusion Engineering and Design, 84(7-11), p.1446 - 1449, 2009/06

 Times Cited Count:3 Percentile:24.54(Nuclear Science & Technology)

In order to validate evaluated nuclear data libraries for fusion reactor designs, various integral benchmark experiments with DT neutrons have been carried out so far on structural and advanced blanket materials at the FNS facility of JAEA. In this study, a neutron spectrum shifter, which will be placed between a sample and the DT neutron source to moderate DT neutrons incident to the sample, was adopted in order to carry out the nuclear data benchmarking induced with several MeV neutrons effectively. In order to estimate effects of the spectrum shifter, the ratio of contribution of initial 14 MeV neutrons in leakage neutron and $$gamma$$-ray spectra was calculated for the experimental configuration at FNS with a modified MCNP-4C code. The calculations were carried out for a Li$$_{2}$$TiO$$_{3}$$ sample with a Be, LiD, or D$$_{2}$$O spectrum shifter. It was found that the Be shifter was superior to others and the contribution of initial 14 MeV neutrons varied depending on material and size of the sample and shifter. The present analysis also suggested that the Be shifter was effective for secondary $$gamma$$-ray experiments.

Oral presentation

Measurement of Zr(n,2n) reaction cross section from the angle correlated neutron spectrum

Shiken, Kimiaki*; Takagi, Satoshi*; Kondo, Keitaro; Matsunaka, Masayuki*; Murata, Isao*; Miyamaru, Hiroyuki*; Ochiai, Kentaro; Nishitani, Takeo

no journal, , 

no abstracts in English

Oral presentation

Design of DT neutron spectrum shifter for integral benchmark experiment in the intermediate energy region

Ota, Masayuki*; Kondo, Keitaro*; Matsunaka, Masayuki*; Miyamaru, Hiroyuki*; Murata, Isao*; Ochiai, Kentaro; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

A Possibility of tokamak based fusion-fission hybrid reactor

Nishio, Satoshi; Hayashi, Takao; Matsunaka, Masayuki*; Murata, Isao*

no journal, , 

A high fusion power density reactor brings some fairly serious problems to the divertor design. A tokamak based fusion-fission hybrid reactor arises both for solving the divertor problems and obtaining sufficient thermal output (GW). We discuss that preferable combinations between the pure fusion power and what the hybrid fuel ought to be. A net tritium breeding ratio (TBR) over unity is added as an indispensable condition. The TBR is drastically improved by introducing a depleted uranium with some used fuel from LWR will be introduced. As a basic strategy for fusion development, with the progress of the divertor technology, the thermal power deriving from fission reaction is to be diminished.

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