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Journal Articles

Neutronics experiments on HCPB and HCLL TBM mock-ups in preparation of nuclear measurements in ITER

Batistoni, P.*; Angelone, M.*; Carconi, P.*; Fischer, U.*; Fleischer, K.*; Kondo, Keitaro; Klix, A.*; Kodeli, I.*; Leichtle, D.*; Petrizzi, L.*; et al.

Fusion Engineering and Design, 85(7-9), p.1675 - 1680, 2010/12

 Times Cited Count:25 Percentile:87.19(Nuclear Science & Technology)

The EU is developing two test blanket modules (TBM), the Helium Cooled Pebble Bed (HCPB) and the Helium Cooled Lithium Lead (HCLL), which will be tested in ITER. Here neutronics experiments with a mockup for HCLL TBM were carried out. Detail distributions of the tritium production rate inside the mockup were measured with various methods. A lithium diamond detector developed as a neutron monitor for fusion devices has also been used as a tritium detector. Activation reaction rates inside the mockup were also measured. These measured data agreed with calculation results buy using MCNP and FENDL-2.1 within 10%, which demonstrated that the prediction accuracy was high. Sensitivity and uncertainty analyses suggested that the uncertainty of the tritium production rate from the nuclear data uncertainty was small, usually below 2%.

Journal Articles

Problems of lead nuclear data in fusion blanket design

Kondo, Keitaro; Murata, Isao*; Klix, A.*; Seidel, K.*; Freiesleben, H.*

Fusion Engineering and Design, 84(7-11), p.1076 - 1086, 2009/06

 Times Cited Count:3 Percentile:26.15(Nuclear Science & Technology)

Several participants of the International Thermonuclear Experimental Reactor (ITER), such as Japan and EU, intend to introduce a Test Blanket Module (TBM) using a liquid lithium lead eutectic, which is used for the neutron multiplier and the tritium breeder. Recently a preliminary experiment in which a LiAlPb assembly was irradiated with 14 MeV neutrons was conducted at Technische Universit$"{a}$t Dresden. We found out that the neutron flux inside the assembly calculated with JENDL-3.3 underestimates an experimental value in the 10-16 MeV region by around 30% and that in the 0.5-5 MeV region by around 15%, while the calculated flux with JEFF-3.1 overestimates the measurement in the 5-10 MeV region by around 20%. In order to reveal a reason of the discrepancy, problems of the nuclear data libraries for lead were investigated. As a result, the following problems of the evaluated libraries were pointed out: The cross sections of the elastic scattering in JENDL-3.3 for lead isotopes are too small and cause a significant underestimation of the neutron flux above 10 MeV, which appeared in the analysis of the above experiment. Inelastic scattering data for $$^{208}$$Pb in JENDL-3.3 reproduce previous experimental double-differential cross section data most well. However, those for the other lead isotopes have some problems and cause a large underestimation of the neutron flux from 0.5 to 5 MeV. The reason of the overestimation in the energy region of 5-10 MeV with JEFF-3.1 is still unclear.

Journal Articles

The Integral experiment on beryllium with D-T neutrons for verification of tritium breeding

Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo

Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01

 Times Cited Count:8 Percentile:53.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Non-destructive analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio

Verzilov, Y. M.; Ochiai, Kentaro; Klix, A.; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo

Journal of Nuclear Materials, 329-333(Part2), p.1337 - 1341, 2004/08

 Times Cited Count:4 Percentile:30.82(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Initial results of neutronics experiments for evaluation of tritium production rate in solid breeding blanket

Nishitani, Takeo; Ochiai, Kentaro; Klix, A.; Verzilov, Y. M.; Sato, Satoshi; Yamauchi, Michinori*; Nakao, Makoto*; Hori, Junichi; Enoeda, Mikio

Proceedings of 20th IEEE/NPSS Symposium on Fusion Engineering (SOFE 2003), p.454 - 457, 2003/10

no abstracts in English

Journal Articles

Neutronics experiments for DEMO blanket at JAERI/FNS

Sato, Satoshi; Ochiai, Kentaro; Hori, Junichi; Verzilov, Y. M.; Klix, A.; Wada, Masayuki*; Terada, Yasuaki*; Yamauchi, Michinori*; Morimoto, Yuichi*; Nishitani, Takeo

Nuclear Fusion, 43(7), p.527 - 530, 2003/07

 Times Cited Count:15 Percentile:46.44(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Radioactivity production around the surface of a cooling water pipe in a D-T fusion reactor by sequential charged particle reactions

Hori, Junichi; Maekawa, Fujio; Wada, Masayuki*; Ochiai, Kentaro; Yamauchi, Michinori*; Morimoto, Yuichi*; Terada, Yasuaki; Klix, A.; Nishitani, Takeo

Fusion Engineering and Design, 63-64, p.271 - 276, 2002/12

 Times Cited Count:2 Percentile:17.59(Nuclear Science & Technology)

In order to the waste management method and the safety design of future D-T fusion reactor, it is important to consider the radioactivity productions via not only primary neutron reactions but also sequential charged particle reactions (SCPR). Especially, on the surface of a coolant channel many recoiled protons are generated by the neutron irradiation with coolant water, so it is apprehensive that the undesirable radioactive nuclide production yields via SCPR are enhanced. In this work, the laminated sample pieces of fusion material foils (V, Fe, W, Ti, Pb, Cu) were made and attached on a polyethylene board to simulate water flowing inside a coolant channel. They were irradiated with D-T neutrons. The effective radioactivity cross section and the depth distribution of the radioactivity production yields due to SCPR were obtained for each material. On the other hand, the estimated values were compared with the experimental ones.

JAEA Reports

Experimental study of material activation of reduced activation ferritic steel F82H by D-T neutron irradiation

Terada, Yasuaki*; Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Klix, A.; Yamauchi, Michinori*; Hori, Junichi; Nishitani, Takeo

JAERI-Research 2002-019, 70 Pages, 2002/10


D-T neutron irradiation experiments have been carried out with a F82H-containing breeding blanket mock-up of a fusion in order to investigate the activation characteristics of F82H low activation stainless steel. We have measured reaction rates producing 54Mn, 56Mn, 51Cr and 187W in foils of F82H, chromium and tungsten. MCNP calculations were done with evaluated nuclear data from the JENDL-3.2 and the FENDL/E-2.0 files and the results were compared with the measured values. The comparison shows that by using the current data files the reaction rates obtained from the calculations will be overestimated by up to 10-20% for 54Mn, 56Mn and 51Cr, up to 30-40% for 187W, respectively. The calculated values for tungsten are different with the evaluated nuclear data library, which shows that the neutron capture cross sections of tungsten have discrepancy in the resonance region for each nuclear data libraries.

Journal Articles

Neutronics experiment of $$^{6}$$Li-enriched breeding blanket with Li$$_{2}$$TiO$$_{3}$$/Be/F82H assembly using D-T neutrons

Ochiai, Kentaro; Klix, A.; Hori, Junichi; Morimoto, Yuichi*; Wada, Masayuki*; Nishitani, Takeo

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1147 - 1150, 2002/08

Thermal blanket type as one of conceptual designs for DEMO-fusion blanket is proposed. We have irradiated the trial blanket assembly which was stratified 95-% enriched Li2TiO3,F82H and beryllium block using Fusion Neutron Source (FNS) and verified the accuracy of these parameters by measurements of tritium and gamma-ray emitted from samples of95-% enriched Li2TiO3 and F82H. We have used the liquid scintillated counter as the method of tritium measurement. Activation foils, NE213, Si-SBD and Fission chamber have usedto measure neutron fluence. Moreover, we have concurrently measured the gamma rays of 56Mn, 54Mn, 187W and 51Cr was produced by 56Fe(n,p), 54Fe(n,p), 186W(n,g), 52Cr(n,2n) and 50Cr(n,g) in F82H. We have used the JENDL Fusion File library and MCNP to verify the accuracy tritium-production rate and 56Mn, 54Mn, 187W and 51Cr. From the results of above experiments, MCNP that uses the JENDL-FF nuclear data library can predict the nuclear parameters such as TPR, Nb, 56Mn, In and 54Mn in the test assemblies within an accuracy of 10%.

Journal Articles

Tritium measurements for $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ breeding blanket experiments with D-T neutrons

Klix, A.; Ochiai, Kentaro; Terada, Yasuaki; Morimoto, Yuichi*; Yamauchi, Michinori*; Hori, Junichi; Nishitani, Takeo

Fusion Science and Technology, 41(3, Part2), p.1040 - 1043, 2002/05

$$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ is one of the candidate materials for the breeding blanket of the fusion DEMO reactor. Therefore, it is necessary to measure the tritium production performance and estimate the accuracy of the measurement method. The JAERI Fusion Neutronics Source (FNS) group has carried out experiments with breeding blanket mock-ups composed of layers of beryllium, ferritic steel F82H and enriched Li$$_{2}$$TiO$$_{3}$$. Pellets of enriched Li$$_{2}$$TiO$$_{3}$$ with a diameter of 12mm and a thickness of 2mm were used as detectors inside the tritium breeding layer. After irradiation, the pellets were dissolved and the tritium activity in the sample solution was measured by liquid scintillation counting. The experimentally obtained tritium production profile in the lithium titanate layer agreed well with MCNP calculations within the estimated error of the measured values (10%). The calculation-experiment ratio was close to one for all samples. Tritium loss from the pellet during storage time (a few days) was experimentally found to be negligible.

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