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Journal Articles

Neutronics experiment on a helium cooled pebble bed (HCPB) breeder blanket mock-up

Batistoni, P.*; Angelone, M.*; Bettinali, L.*; Carconi, P.*; Fischer, U.*; Kodeli, I.*; Leichtle, D.*; Ochiai, Kentaro; Perel, R.*; Pillon, M.*; et al.

Fusion Engineering and Design, 82(15-24), p.2095 - 2104, 2007/10

 Times Cited Count:22 Percentile:82.92(Nuclear Science & Technology)

A neutronics experiment has been performed in the frame of European Fusion Technology Program on a mock-up of the EU Test Blanket Module (TBM), Helium Cooled Pebble Bed (HCPB) concept, with the objective to validate the capability of nuclear data to predict nuclear responses, such as the tritium production rate (TPR), with qualified uncertainties. In the experiment, the TPR has been measured using Li$$_{2}$$CO$$_{3}$$ pellets at various depths at two symmetrical positions at each depth, one in the upper and one in the lower breeder cassette. Three independent measurements were performed by ENEA, TUD/VKTA and JAEA. The neutron flux in the beryllium layer was measured as well using activation foils.

Journal Articles

Measurement of tritium production rate in water cooled pebble bed multi-layered blanket mockup by DT neutron irradiation experiment

Sato, Satoshi; Ochiai, Kentaro; Verzilov, Y.*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo; Konno, Chikara

Nuclear Fusion, 47(7), p.517 - 521, 2007/07

 Times Cited Count:18 Percentile:57.13(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Neutronics experimental study on tritium production in solid breeder blanket mockup with neutron reflector

Sato, Satoshi; Verzilov, Y.*; Ochiai, Kentaro; Wada, Masayuki*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Seki, Masakazu; Oginuma, Yoshikazu*; Kawabe, Masaru*; et al.

Journal of Nuclear Science and Technology, 44(4), p.657 - 663, 2007/04

 Times Cited Count:7 Percentile:49.85(Nuclear Science & Technology)

Neutronics experiments have been performed for the solid breeder blanket using a DT neutron source at the FNS facility in JAEA. We have applied the blanket mockup composed of two enriched Li$$_{2}$$TiO$$_{3}$$ and three beryllium layers, and measured the detailed spatial distribution of the tritium production rate (TPR) using enriched Li$$_{2}$$CO$$_{3}$$ pellets. TPRs in the pellets have been measured by a liquid scintillation counter. Experiments have been done under a condition with a neutron reflector surrounding the DT neutron source. Numerical simulations have been performed using the MCNP-4C with the FENDL-2.0 and JENDL-3.3. The ranges of ratios of calculation results to experimental ones (C/Es) are 0.97-1.17 concerning with local TPR, and 1.04-1.09 for the integrated tritium production. It is found that the total integrated tritium production, which corresponds to tritium breeding ratio, can be predicted within uncertainty of 10% using the Monte Carlo calculation code and latest nuclear data libraries.

Journal Articles

Surface analysis for the TFTR Armor tile exposed to D-T plasmas using nuclear technique

Kubota, Naoyoshi; Ochiai, Kentaro; Kutsukake, Chuzo; Hayashi, Takao; Shu, Wataru; Kondo, Keitaro; Verzilov, Y.*; Sato, Satoshi; Yamauchi, Michinori; Nishi, Masataka; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 7 Pages, 2007/03

Fuel and impurity particles show complicated behavior on the surface of plasma facing components (PFC) in fusion devices. The study is important for the design of the fuel recycling, safety management of the tritium inventory, etc. Quantitative measurements of hydrogen and lithium isotopes together with other impurities on the PFC surface exposed to D-T plasmas in TFTR were performed using the deuteron-induced nuclear reaction analysis, imaging plate method, full combustion method and activation analysis. The tritium depth profile was different from deuterium one. The surface tritium largely contributed to the whole tritium in the sample. On the other hand, the retained amount of lithium-6 was lager than that of lithium-7. This relates to the injection of enriched lithium-6 pellets in some campaigns. No other impurities were detected. So the large amount of tritium remained near the surface and did not diffuse more deeply, which gives a bright prospect for tritium safety.

Journal Articles

Experimental study on nuclear properties of water cooled pebble bed blanket

Sato, Satoshi; Verzilov, Y.*; Ochiai, Kentaro; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo; Konno, Chikara

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

no abstracts in English

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

Development of a new fusion power monitor based on activation of flowing water

Verzilov, Y. M.; Nishitani, Takeo; Ochiai, Kentaro; Kutsukake, Chuzo; Abe, Yuichi

Fusion Engineering and Design, 81(8-14), p.1477 - 1483, 2006/02

 Times Cited Count:2 Percentile:18.25(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress in the blanket neutronics experiments at JAERI/FNS

Sato, Satoshi; Verzilov, Y. M.; Ochiai, Kentaro; Nakao, Makoto*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo

Fusion Engineering and Design, 81(8-14), p.1183 - 1193, 2006/02

 Times Cited Count:17 Percentile:77.1(Nuclear Science & Technology)

no abstracts in English

Journal Articles

International benchmark activity of tritium measurement of blanket neutronics

Ochiai, Kentaro; Verzilov, Y. M.; Nishitani, Takeo; Batistoni, P.*; Seidel, K.*

Fusion Science and Technology, 48(1), p.378 - 381, 2005/07

 Times Cited Count:7 Percentile:47.08(Nuclear Science & Technology)

To evaluate the measurement accuracy of the tritium production from $$^{6}$$LiLi(n,t)$$^{4}$$He reactions, an international benchmark program was initiated again under the frame work of an IEA fusion neutronics subtask from 2003. JAERI, ENEA and Technical University of Dresden (TUD) are participating in the activity. This program consists of the calibration of the tritium measurement systems and the verification of the measurement accuracies of the tritium production from $$^{7}$$Li(n,nt)$$^{4}$$He and $$^{6}$$LiLi(n,t)$$^{4}$$He reactions. We have completed the calibration of the measurement system with tritium standard water (HTO) and blind HTO samples. From the results, the scattering of the calibration was within 1.5 %.

Journal Articles

Methods for tritium production rate measurement in design-oriented blanket experiments

Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo

Fusion Science and Technology, 48(1), p.650 - 653, 2005/07

 Times Cited Count:7 Percentile:47.08(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental studies on tungsten-armour impact on nuclear responses of solid breeding blanket

Sato, Satoshi; Nakao, Makoto*; Verzilov, Y. M.; Ochiai, Kentaro; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo

Nuclear Fusion, 45(7), p.656 - 662, 2005/07

 Times Cited Count:8 Percentile:30.16(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Neutronics experiments using small partial mockups of the ITER test blanket module with a solid breeder

Sato, Satoshi; Verzilov, Y. M.; Nakao, Makoto*; Ochiai, Kentaro; Wada, Masayuki*; Nishitani, Takeo

Fusion Science and Technology, 47(4), p.1046 - 1051, 2005/05

 Times Cited Count:12 Percentile:65.49(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Integral experiments for verification of tritium production on the beryllium/lithium titanate blanket mock-up with a one-breeder layer

Verzilov, Y. M.; Sato, Satoshi; Nakao, Makoto*; Ochiai, Kentaro; Wada, Masayuki*; Nishitani, Takeo

JAERI-Research 2004-015, 55 Pages, 2004/10

JAERI-Research-2004-015.pdf:3.29MB

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

JAEA Reports

Analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio

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

JAERI-Research 2004-005, 30 Pages, 2004/03

JAERI-Research-2004-005.pdf:1.93MB

no abstracts in English

Journal Articles

A New approach to the D-T neutron monitor using water flow

Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo

Journal of Nuclear Science and Technology, 41(Suppl.4), p.395 - 398, 2004/03

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

JAEA Reports

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

Experimental study on beryllium-7 production via sequential reactions in lithium-containing compounds irradiated by 14-MeV neutrons

Maekawa, Fujio; Verzilov, Y.M.*; Smith, D. L.*; Ikeda, Yujiro

Journal of Nuclear Materials, 283-287(Part.2), p.1448 - 1452, 2000/12

 Times Cited Count:5 Percentile:38.85(Materials Science, Multidisciplinary)

no abstracts in English

25 (Records 1-20 displayed on this page)