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JAEA Reports

An Irradiation test of heat-resistant ceramic composite materials, 2; Interim report on post-irradiation examinations of the second and third preliminary test, 98M-41A, 99M-30A

Baba, Shinichi; Nemoto, Makoto*; Sozawa, Shizuo; Yamaji, Masatoshi*; Ishihara, Masahiro; Sawa, Kazuhiro

JAERI-Tech 2005-055, 157 Pages, 2005/09

JAERI-Tech-2005-055.pdf:19.06MB

The Japan Atomic Energy Research Institute (JAERI) has been carrying out the research on radiation damage mechanism of heat-resistant ceramics composite materials, as one of the subjects of the innovative basic research on high temperature engineering using the High Temperature Engineering Test Reactor (HTTR). A series of preliminary irradiation tests is being made using the Japan Materials Testing Reactor (JMTR). The present report describes results of post-irradiation examinations so far on specimens irradiated in the second and third capsule, designated 98M-41A and 99M-30A, to fast neutron fluences of 1.0$$times$$10$$^{25}$$m$$^{-2}$$(E$$>$$1MeV) at temperatures of 973K-1173K and 1273K-1473K. The PIE were conducted as the fundamental statistics index of the diametral dimensions for irradiated specimen, irradiation induced dimensional change rate and thermal expansion rate.

JAEA Reports

Failure probability analysis on mercury target vessel

Ishikura, Shuichi*; Shiga, Akio*; Futakawa, Masatoshi; Kogawa, Hiroyuki; Sato, Hiroshi; Haga, Katsuhiro; Ikeda, Yujiro

JAERI-Tech 2005-026, 65 Pages, 2005/03

JAERI-Tech-2005-026.pdf:2.86MB

Failure probability analysis was carried out to estimate the lifetime of the mercury target which will be installed into the JSNS (Japan spallation neutron source) in J-PARC (Japan Proton Accelerator Research Complex). The lifetime was estimated as taking loading condition and materials degradation into account. Considered loads imposed on the target vessel were the static stresses due to thermal expansion and static pre-pressure on He-gas and mercury and the dynamic stresses due to the thermally shocked pressure waves generated repeatedly at 25 Hz. Materials used in target vessel will be degraded by the fatigue, neutron and proton irradiation, mercury immersion and pitting damages, etc. The imposed stresses were evaluated through static and dynamic structural analyses. The material-degradations were deduced based on published experimental data. As results, it was quantitatively confirmed that the failure probability for the lifetime expected in the design is very much lower, 10$$^{-11}$$ in the safety hull, meaning that it will be hardly failed during the design lifetime. On the other hand, the beam window of mercury vessel suffered with high-pressure waves exhibits the failure probability of 12%. It was concluded, therefore, that the leaked mercury from the failed area at the beam window is adequately kept in the space between the safety hull and the mercury vessel to detect mercury-leakage sensors.

Journal Articles

Present status of the liquid lithium target facility in the international fusion materials irradiation facility (IFMIF)

Nakamura, Hiroo; Riccardi, B.*; Loginov, N.*; Ara, Kuniaki*; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; et al.

Journal of Nuclear Materials, 329-333(1), p.202 - 207, 2004/08

 Times Cited Count:14 Percentile:68.23(Materials Science, Multidisciplinary)

International Fusion Materials Irradiation Facility (IFMIF), being developed by EU, JA, RF and US, is a deuteron-lithium (Li) reaction neutron source for fusion materials testing. In the end of 2002, 3 year Key Element technology Phase (KEP) to reduce the key technology risk factors has been completed. This paper describes these KEP tasks results. To evaluate Li flow characteristics, a water and Li flow experiments have been done. To develop Li purification system, evaluation of nitrogen and tritium gettering materials have been done. Conceptual design of remote handling and basic experiment have been donde. In addition, safety analysis and diganostics design have been done. In the presentation, the latest design and future prospects will be also summarized.

Journal Articles

Effects of neutron irradiation on some superplastic characteristics of tetragonal zirconia polycrystals containing 3 mol% yttria

Shibata, Taiju; Ishihara, Masahiro; Motohashi, Yoshinobu*; Ito, Tsutomu*; Baba, Shinichi; Kikuchi, Makoto*

Materials Transactions, 45(8), p.2580 - 2583, 2004/08

 Times Cited Count:3 Percentile:28.51(Materials Science, Multidisciplinary)

Fast neutrons (energy $$>$$ 1.6$$times$$10$$^{23}$$ J) were irradiated to tetragonal zirconia polycrystals containing 3 mol% yttria (3Y-TZP) at the fluence levels of 2.5$$times$$10$$^{24}$$ (Light irradiation) and 4.3$$times$$10$$^{24}$$ (Heavy irradiation) m$$^{-2}$$. The irradiation caused no significant swelling in the 3Y-TZP specimens. After the neutron irradiation, superplastic characteristics were examined by tensile tests at a temperature range from 1623 to 1773 K with initial strain rates ranging from 5.0$$times$$10$$^{-4}$$ to 1.67$$times$$10$$^{-2}$$s$$^{-1}$$. It was found that the elongation to fracture of the irradiated specimens was quite small in comparison with the unirradiated ones. The apparent activation energy for the superplastic flow of the irradiated 3Y-TZP was fairly high, i.e., 781 and 693 kJ・mol$$^{-1}$$ for Light and Heavy irradiations, respectively. Atomic displacement damages and defects in the 3Y-TZP caused by the irradiation were thought to be main causes of these property changes.

Journal Articles

Damage evaluation techniques for FBR and LWR structural materials based on magnetic and corrosion properties along grain boundaries

Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*

Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06

JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.

JAEA Reports

Estimation of tritium permeation through reduced-activation ferritic steel at IFMIF target backwall damaged by neutron irradiation

Matsuhiro, Kenjiro; Ando, Masami; Nakamura, Hiroo; Takeuchi, Hiroshi

JAERI-Research 2004-003, 12 Pages, 2004/03

JAERI-Research-2004-003.pdf:0.85MB

The effect of neutron irradiation damage on tritium permeation through reduced-activation ferritic steel (F82H) at IFMIF target backwall has been estimated. From the results, it has been found that the effective diffusion coefficient of hydrogen in F82H will decrease by 10 % to 20 % under neutron irradiation. Therefore, the amount of tritium permeation for several hundred seconds at the beginning of permeation will be smaller than 80 % to 90 % of that before neutron irradiation. The amount of tritium permeation of F82H at IFMIF target backwall is 1.3x10$$^{-11}$$ g/d (4.7x10$$^{3}$$ Bq/d). It is 30 times larger than that of 316SS, and is about 8 % of tritium permeation at main loop of IFMIF.

Journal Articles

Lattice parameter expansion by self-irradiation damage of $$^{244}$$Cm-$$^{240}$$Pu oxide and mononitride

Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Ogawa, Toru; Numata, Masami; Kizaki, Minoru

Journal of Nuclear Science and Technology, 39(Suppl.3), p.842 - 845, 2002/11

no abstracts in English

Journal Articles

Effects of 293-1573K annealing on some properties of 3Y-TZP irradiated with Zr ions

Sakuma, Takaaki*; Motohashi, Yoshinobu*; Kobayashi, Tomokazu*; Harjo, S.*; Shibata, Taiju; Ishihara, Masahiro; Baba, Shinichi; Hoshiya, Taiji

Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2002) Koen Rombunshu (No.020-3), p.125 - 126, 2002/09

no abstracts in English

Journal Articles

Study on creep-fatigue life of irradiated austenitic stainless steel

Ioka, Ikuo; Miwa, Yukio; Tsuji, Hirokazu; Yonekawa, Minoru; Takada, Fumiki; Hoshiya, Taiji

JSME International Journal, Series A, 45(1), p.51 - 56, 2002/01

The low cycle creep-fatigue test with tensile strain hold of the austenitic stainless steel irradiated to 2dpa was carried out at 823K in vacuum. The applicability of creep-fatigue life prediction methods to the irradiated specimen was examined. The fatigue life on the irradiated specimen without tensile strain hold time was reduced by a factor of 2-5 in comparison with the unirradiated specimen. The fraction of intergranular fracture increased with increasing strain hold time. The decline in fatigue life of the irradiated specimen with tensile strain hold was almost equal to that of the unirradiated specimen. For the irradiated specimen, the time fraction damage rule trends to yield unsafe estimated lives and the ductility exhaustion damage rule trends to yield generous results. However, all of data were predicted within a factor of three on life by the linear damage rule.

Journal Articles

Post-irradiation annealing and re-irradiation technique for LWR reactor pressure vessel material

Matsui, Yoshinori; Ide, Hiroshi; Itabashi, Yukio; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Abe, Shinichi; Inoue, Shuichi; Shimizu, Michio; Iwamatsu, Shigemi; Watanabe, Naoki*; et al.

KAERI/GP-195/2002, p.33 - 40, 2002/00

Studies on the irradiation damage of the material of the RPV are inevitable for the LWR. Recently, the researches of annealing effect on the irradiation damage of RPV material were extensively carried out using specimens irradiated in the JMTR of the JAERI. As the next step, an annealing test of irradiated specimens and re-irradiation of annealed specimens were planned. The aim of the test is to evaluate the effect of annealing by comparing the damage of irradiated specimen, its recovery by annealing and the damage after re-irradiation. For the re-irradiation test of this study, JAERI developed a new capsule in which the specimens can be exchanged before and after annealing, and, re-irradiated afterward. The development of the capsule consisted of the design and fabrication of airtight connector for thermocouples and mechanical seal device which was fit to remote handling. Remote operation procedures for handling the radioactive capsule and for exchanging specimens were carefully performed. The results of the re-irradiation proved that the development was technically successful.

Journal Articles

Present status and future programme of HTTR and the innovative basic research on high temperature engineering

Hayashi, Kimio; Ishihara, Masahiro; Shibata, Taiju; Ishino, Shiori*; Terai, Takayuki*; Ito, Hisayoshi; Tagawa, Seiichi*; Katsumura, Yosuke*; Yamawaki, Michio*; Shikama, Tatsuo*; et al.

Proceedings of 1st Information Exchange Meeting on Basic Studies on High-Temperature Engineering, p.41 - 58,268, 1999/09

no abstracts in English

Journal Articles

Japanese contribution to ITER task of irradiation tests on diagnostics components

Nishitani, Takeo; Ishitsuka, Etsuo; Kakuta, Tsunemi; Sagawa, Hisashi; Oyama, Yukio; *; Sugie, Tatsuo; Noda, Kenji; Kawamura, Hiroshi; Kasai, Satoshi

Fusion Engineering and Design, 42, p.443 - 448, 1998/00

 Times Cited Count:22 Percentile:84.39(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Effects of primary recoil (PKA) energy spectrum on radiation damage in FCC metals

Iwata, Tadao*; Iwase, Akihiro

JAERI-Research 97-073, 45 Pages, 1997/10

JAERI-Research-97-073.pdf:1.55MB

no abstracts in English

Journal Articles

Nuclear design for fusion reactors

*; Seki, Yasushi; Sato, Satoshi; *

Purazuma, Kaku Yugo Gakkai-Shi, 71(10), p.987 - 1001, 1995/10

no abstracts in English

Journal Articles

Development of neutron damage studies; US-Japan joint irradiation experiment on structural materials

Hishinuma, Akimichi

Purazuma, Kaku Yugo Gakkai-Shi, 70(7), p.719 - 725, 1994/07

no abstracts in English

Journal Articles

Self-irradiation damage in PuN

Okamoto, Yoshihiro; Maeda, Atsushi;

Journal of Nuclear Materials, 206, p.94 - 96, 1993/00

 Times Cited Count:3 Percentile:61.64(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

X-ray diffraction studies of self-ion irradiated synthetic single crystal diamond

Maeta, Hiroshi; Haruna, K.*; B.Lu*; Ono, Fumihisa*

Nuclear Instruments and Methods in Physics Research B, 80-81, p.1477 - 1479, 1993/00

 Times Cited Count:6 Percentile:58.17(Instruments & Instrumentation)

no abstracts in English

Journal Articles

On the low-temperature electron irradiation experiments

Iwata, Tadao

KURRI-TR-351, p.90 - 104, 1991/00

no abstracts in English

Journal Articles

Magnetic flux motion of superconducting Bi-Sr-Ca-Cu-O films after ion irradiation

Hoshiya, Taiji; Takamura, Saburo; ; *

Japanese Journal of Applied Physics, 29(8), p.L1443 - L1445, 1990/08

 Times Cited Count:4 Percentile:30.22(Physics, Applied)

no abstracts in English

32 (Records 1-20 displayed on this page)