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Journal Articles

The Role of silicon on solute clustering and embrittlement in highly neutron-irradiated pressurized water reactor surveillance test specimens

Takamizawa, Hisashi; Hata, Kuniki; Nishiyama, Yutaka; Toyama, Takeshi*; Nagai, Yasuyoshi*

Journal of Nuclear Materials, 556, p.153203_1 - 153203_10, 2021/12

 Times Cited Count:3 Percentile:44.61(Materials Science, Multidisciplinary)

Solute clusters (SCs) formed in pressurized water reactor surveillance test specimens neutron-irradiated to a fluence of 1 $$times$$ 10$$^{20}$$ n/cm$$^{2}$$ were analyzed via atom probe tomography to understand the effect of silicon on solute clustering and irradiation embrittlement of reactor pressure vessel steels. In high-Cu bearing materials, Cu atoms were aggregated at the center of cluster surrounded by the Ni, Mn, and Si atoms like a core-shell structure. In low-Cu bearing materials, Ni, Mn, and Si atoms formed cluster and these solutes were not comprised core-shell structure in SCs. While the number of Cu atoms in clusters was decreased with decreasing nominal Cu content, the number of Si atoms had clearly increased. The cluster radius ($$r$$) and number density ($$N_{d}$$) decreased and increased, respectively, with increasing nominal Si content. The shift in the reference temperature for nil-ductility transition ($$Delta$$RT$$_{NDT}$$) showed a good correlation with the square root of volume fraction ($$V_{f}$$) multiplied by r ($$sqrt{V_{f}times {r}}$$). This suggested that the dislocation cutting through the particles mechanism dominates the precipitation hardening responsible for irradiation embrittlement. The negative relation between the nominal Si content and $$Delta$$RT$$_{NDT}$$ indicated that increasing of nominal Si content reduces the degree of embrittlement.

JAEA Reports

Determination of neptunium in neptunium-uranium-plutonium mixed oxide fuel by spectrophotometry.

; ; ; ; ; *; *

JNC TN8400 2001-026, 29 Pages, 2001/12

JNC-TN8400-2001-026.pdf:0.99MB

The measurement condition by spectrophotometry was evaluated to measure Np content in MOX fuel containing Np. The Np concentration was obtained by measuring the 727nm absorption peak, after the valence of Np in the sample solution was adjusted to the Np(Ⅳ). The calibration curve showed the linearity up to Np concentration 0.8mg/ml. Though Pu and U quantity were respectively added to the Np solution to 30 times and 60 times of Np concentration, there was no effect to the Np analysis. By using this method, relative standard deviation (RSD) of the analyzed values of Np content for 2%Np - MOX fuel was about 4%. In addition, It was confirmed that the Np content could be measured without separating Np from Pu and U. This method can be sufficiently applied as a quick simple method to analyze Np content in MOX fuel containing Np.

JAEA Reports

None

PNC TJ1615 97-001, 5 Pages, 1997/03

PNC-TJ1615-97-001.pdf:0.32MB

no abstracts in English

JAEA Reports

None

PNC TJ1615 95-002, 5 Pages, 1995/03

PNC-TJ1615-95-002.pdf:0.28MB

no abstracts in English

JAEA Reports

Evaluation of in-situ coated boron film in JT-60U; Portable sample stage system and its application to evaluate the coated boron film

Yagyu, Junichi; Arai, Takashi; Ogiwara, Norio; Saido, Masahiro;

JAERI-M 93-249, 43 Pages, 1994/01

JAERI-M-93-249.pdf:2.59MB

no abstracts in English

JAEA Reports

None

Kurosawa, Ryuhei*

PNC TJ1615 93-002, 13 Pages, 1993/03

PNC-TJ1615-93-002.pdf:0.35MB

no abstracts in English

JAEA Reports

Survey on the behavior of radioactive substance in the atmosphere

*; *; *; Iida, Takao*; *; *

PNC TJ1545 93-005, 36 Pages, 1993/03

PNC-TJ1545-93-005.pdf:1.09MB

no abstracts in English

JAEA Reports

The Effects of water environments on crack growth behavior of LWR pressure vessel steels

Onizawa, Kunio; ; ;

JAERI-M 90-202, 33 Pages, 1990/11

JAERI-M-90-202.pdf:1.15MB

no abstracts in English

Journal Articles

Effect of carbon on microstructure in Ti-modified type 316 stainless steels irradiated with helium ions

Suzuki, K.; Katano, Y.; Aruga, T.; Hamada, S.; Shiraishi, K.

Journal of Nuclear Materials, 133-134, p.585 - 589, 1985/00

 Times Cited Count:2 Percentile:37.48(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Influence of Mn Content on Corrosion Behavior Ni-Cr-W Alloys in Simulated VHTR Helium Environment

Shindo, Masami; Kondo, Tatsuo

JAERI-M 83-118, 18 Pages, 1983/07

JAERI-M-83-118.pdf:0.78MB

no abstracts in English

JAEA Reports

Effects of Thermal Neutron Irradiation on Ductility of Austenitic Heat Resisting Alloys for HTR Application

; Kondo, Tatsuo; Ogawa, Yutaka

JAERI-M 83-117, 14 Pages, 1983/07

JAERI-M-83-117.pdf:0.66MB

no abstracts in English

JAEA Reports

Effect of Thermal Neutron Irradiation on Mechanical Properties of Alloys for HTR core Applications

Ogawa, Yutaka; Kondo, Tatsuo; ;

JAERI-M 8154, 12 Pages, 1979/02

JAERI-M-8154.pdf:0.54MB

no abstracts in English

Journal Articles

Gas content of graphites, 1

; ;

Nihon Genshiryoku Gakkai-Shi, 3(12), p.942 - 948, 1961/00

no abstracts in English

14 (Records 1-14 displayed on this page)
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