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Journal Articles

Material properties evaluation on radiation shielding lead glasses irradiated by pulsed laser

Wakui, Takashi; Yamasaki, Kazuhiko*; Futakawa, Masatoshi

Advanced Experimental Mechanics, 7, p.103 - 109, 2022/08

As part of the development of technique to cut and reduce the volume of highly radioactive components in the closed space, pulsed Nd:YAG laser was irradiated to radiation shielding glasses with the different lead content in the different irradiation condition; power and number of irradiation. The large black irradiated area with concave shape and cracks around it occurred with an increase of the lead content, power and number of irradiation. General mechanical properties in unirradiated and irradiated area were investigated to investigate the influence of mechanical properties on the irradiation damage. The thermal impact fracture toughness calculated based on the estimated mechanical properties decreased with increasing the lead content. The micro hardness in black irradiated area was 10% smaller than that in the unirradiated area. The change of the mechanical property due to the laser irradiation was confirmed.

Journal Articles

Effect of pulsed laser irradiation on the micro-plastic behavior of radiation shielding lead glasses

Wakui, Takashi; Yamasaki, Kazuhiko*; Futakawa, Masatoshi

Jikken Rikigaku, 22(2), p.96 - 104, 2022/06

Pulsed laser irradiation and indentation tests on radiation shielding glasses and a lead-free glass were carried out. The size of irradiation damage of the glass with high lead content was larger than that with low content. The micro plastic behavior of glasses was quantitatively determined using the inverse analyses based on indentation results. Flow stress decreased with an increase of lead content and that in irradiated area was lower than that in unirradiated area. On the other hand, plastic flow resistance increased with an increase of the lead content and that in irradiated area was higher than that in unirradiated area. Fracture energy and critical size of plastic zone around tip of crack in unirradiated and irradiated areas were calculated based on experimental results including constants evaluated using the inverse analysis. These values decreased with an increase of the lead content and these values in irradiated area were lower than that in unirradiated area.

Journal Articles

Necessity (proposal) of secure detection system of nuclear materials and interior inspection systems of detected / suspicious objects in non-destructive manner for safe dismantling

Seya, Michio; Hajima, Ryoichi*; Kureta, Masatoshi

Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu (CD-ROM), 10 Pages, 2017/02

Large size freight cargo containers are the most volunurable items from nuclear security points of view because of their large volume and weight of cargo inside for hiding heavily shielded objects. For strengthning nuclear security, secure detection of NMs in heavily shielded objects, and safe handling (dismatlement) of detected / suspicious objects for taking out of NMs, are essential. These require the following things, (1) Introduction of secure detection system of NMs, (2) Inspection of deteiled and interior structures of detected objects, (3) Rough chracterization of NMs (for nuclear bomb or RDD etc.) / Confirmation of existence of explosives etc.. By using information obtained by interior inspections, safe dismantlement of objects and taking NMs out are possible. In this papaer, we propose a combined system of X-ray scanning system with NRF-based NDD system using monochromatic $$gamma$$-ray beam not only as a secure detection system of NMs but also interior inspection system (covering (1) and (2)). Also we propose active neutron NDA system using a D-T source for interior inspection of NM part (covering (3)).

Journal Articles

Engineering design and control scenario for steady-state high-beta operation in national centralized tokamak

Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02

 Times Cited Count:1 Percentile:9.98(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Field emission-type scanning electron microscope for examination of irradiated fuels

Yasuda, Ryo; Mita, Naoaki; Nishino, Yasuharu; Nakata, Masahito; Nozawa, Yukio; Harada, Katsuya; Kushida, Teruo; Amano, Hidetoshi

Nuclear Technology, 151(3), p.341 - 345, 2005/09

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

The Field Emission type Scanning Electron Microscope (FE-SEM), which is one of effective tools for observation of micr-structures, was installed at the Reactor Fuel Examination Facility (RFEF) in JAERI. The FE-SEM is equipped in a large shield vessel with remote handling systems to keep safety of operators and is modified to enable to manipulate high radioactive materials. The Energy Dispersive Spectrometer (EDS) with radiation-shielded collimators has been also equipped on the FE-SEM to determine element compositions of the observed material samples. Characterization tests were carried out using deposited gold film and Zircaloy cladding tubes with hydrides to confirm the machine performance after the modifications. In the results of the tests, high-resolution images without some noises and fogs were obtained with high magnification above 10,000. Those results show that the FE-SEM keeps the high performance after some improvements and modifications for shielding $$gamma$$-rays and handling radioactive samples.

Journal Articles

Evaluation of radiation shielding, nuclear heating and dose rate for JT-60 superconducting modification

Morioka, Atsuhiko; Sakasai, Akira; Masaki, Kei; Ishida, Shinichi; Miya, Naoyuki; Matsukawa, Makoto; Kaminaga, Atsushi; Oikawa, Akira

Fusion Engineering and Design, 63-64, p.115 - 120, 2002/12

 Times Cited Count:11 Percentile:58.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Decay heat measurement of fusion related materials in an ITER-like neutron field

Morimoto, Yuichi*; Ochiai, Kentaro; Maekawa, Fujio; Wada, Masayuki*; Nishitani, Takeo; Takeuchi, Hiroshi

Journal of Nuclear Materials, 307-311(Part2), p.1052 - 1056, 2002/12

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

Decay heat is one of the most important factors for the safety aspect of ITER. Especially, prediction of decay heat with uncertainty less than 15% for the three most important materials, i.e., copper, type-316 stainless steel (SS-316) and tungsten, is strongly requested by designers of ITER. To provide experimental decay heat data needed for validation of decay heat calculations for SS316 and copper, an experiment was conducted as the ITER/EDA task T-426. An ITER-like neutron field was constructed, and decay heat source distributions in thick copper and SS316 plates were measured with Whole Energy Absorption Spectrometer. The measured decay heat distributions in the thick sample plates were compared with the predicted values by MCNP calculations. It was found that the use of an effective activation cross section calculated by MCNP was needed to consider the self-shielding effects and, for both cases, MCNP calculations could predict decay heat adequately.

Journal Articles

Rise-to-power test of the HTTR (High Temperature Engineering Test Reactor)

Fujikawa, Seigo; Okubo, Minoru; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.361 - 372, 2002/12

no abstracts in English

JAEA Reports

Shielding calculation constants for use in effective dose evaluation for photons, neutrons and bremsstrahlung from beta-ray

Sakamoto, Yukio; Endo, Akira; Tsuda, Shuichi; Takahashi, Fumiaki; Yamaguchi, Yasuhiro

JAERI-Data/Code 2000-044, 191 Pages, 2001/01

JAERI-Data-Code-2000-044.pdf:7.19MB

no abstracts in English

JAEA Reports

None

; ; ; Iguchi, Yukihiro; Matsui, Yuji;

JNC TN3410 2000-014, 43 Pages, 2000/09

JNC-TN3410-2000-014.pdf:2.37MB

None

JAEA Reports

Simplified shield calculation system for high-intensity proton accelerators

Masumura, Tomomi*; Nakashima, Hiroshi; Nakane, Yoshihiro; Sasamoto, Nobuo

JAERI-Data/Code 2000-026, 40 Pages, 2000/06

JAERI-Data-Code-2000-026.pdf:7.21MB

no abstracts in English

JAEA Reports

Investigation of water content in primary upper shield of High Temperature Engineering Test Reactor (HTTR)

Sumita, Junya; Sawa, Kazuhiro; Mogi, Haruyoshi; ; Kitami, Takayuki; Akutsu, Yoichi; *; *; *

JAERI-Research 99-054, p.41 - 0, 1999/09

JAERI-Research-99-054.pdf:1.19MB

no abstracts in English

JAEA Reports

Analysis on temperature rise of primary upper shielding in HTTR

Ogawa, Masuro; Shiina, Yasuaki; Fumizawa, Motoo; Takeda, Tetsuaki; Takada, Shoji; Kubo, Shinji; Inaba, Yoshitomo

JAERI-Tech 98-062, 126 Pages, 1999/01

JAERI-Tech-98-062.pdf:5.95MB

no abstracts in English

JAEA Reports

None

Nogami, Yoshitaka; ; ; ; Tobita, Noriyuki;

PNC TN8410 93-200, 78 Pages, 1993/06

PNC-TN8410-93-200.pdf:2.7MB

None

Journal Articles

Second version of Japanese evaluated nuclear data library,JENDL-2

Kikuchi, Yasuyuki; Nakagawa, Tsuneo; Asami, Tetsuo; *; *; *

Journal of Nuclear Science and Technology, 22(8), p.593 - 603, 1985/00

 Times Cited Count:13 Percentile:47.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Charge accumulation in radiation shielding glass due to gamma-ray irradiation

; ; ; ; *; *

EIM-82-24, p.9 - 18, 1982/00

no abstracts in English

JAEA Reports

Group Constants for $$^{2}$$$$^{3}$$$$^{2}$$Th with 70 and 25group Structures

Nakagawa, Masayuki; *; *; *; *

JAERI-M 4927, 22 Pages, 1972/08

JAERI-M-4927.pdf:0.81MB

no abstracts in English

Oral presentation

Evaluation of neutron instruments shield in J-PARC Materials and Life Science Experimental Facility

Oi, Motoki; Harada, Masahide; Kai, Tetsuya; Aizawa, Kazuya; Sato, Koichi; Masuyama, Koichi; Kasugai, Yoshimi

no journal, , 

In the J-PARC Materials and Life Science Experimental Facility (MLF), material science experiments using muon and neutron beam are performed. In the MLF, proton beam power was 300KW at May 2014 and it is planning to enhance to 1MW. For proton beam enhancement, we performed evaluation of the shielding performance of the neutron beam instruments. As a result, dose on the shield surface of 16 neutron instruments are sufficiently low for 1MW proton beam operation. However, 4 neutron instruments show high dose rate in particular neutron beam conditions. For these neutron instruments, we have checked the drawings and recalculate the shielding performance and considered a cause. Then based on the measurement results, some shield are added for these four neutron instruments and dose rate are reduced sufficiently to 1MW proton beam operation.

Oral presentation

Shielding design for transport cask of mercury target vessel irradiated at J-PARC

Harada, Masahide; Uchida, Toshitsugu; Sekijima, Mitsuaki; Haga, Katsuhiro; Kogawa, Hiroyuki; Kinoshita, Hidetaka; Takada, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Trial manufacture and study of the shielding bodies that can be easily installed on curved surfaces and flat surfaces

Hayashi, Hirokazu; Matsushima, Akira; Nozaki, Tatsuo

no journal, , 

no abstracts in English

25 (Records 1-20 displayed on this page)