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Journal Articles

Laser-driven proton generation with a thin-foil target

Sagisaka, Akito; Pirozhkov, A. S.; Mori, Michiaki; Yogo, Akifumi; Ogura, Koichi; Orimo, Satoshi; Nishiuchi, Mamiko; Ma, J.*; Kiriyama, Hiromitsu; Kanazawa, Shuhei; et al.

NIFS-PROC-85, p.30 - 33, 2011/02

The experiment of proton generation is performed for developing the laser-driven ion source. We observe proton signals in the laser-plasma interaction by using a thin-foil target. To get higher energy protons the size of the preformed plasma is reduced by changing the laser contrast level. In the high-contrast laser pulse case the maximum energy of the protons generated at rear side of the target increases.

Journal Articles

Proton generation and terahertz radiation from a thin-foil target with a high-intensity laser

Sagisaka, Akito; Pirozhkov, A. S.; Mori, Michiaki; Yogo, Akifumi; Ogura, Koichi; Orimo, Satoshi; Nishiuchi, Mamiko; Ma, J.*; Kiriyama, Hiromitsu; Kanazawa, Shuhei; et al.

Reza Kenkyu, 38(9), p.702 - 705, 2010/09

High-intensity laser and thin-foil interactions produce high-energy particles, hard X-ray, high-order harmonics, and terahertz (THz) radiation. A proton beam driven by a high-intensity laser has received attention as a compact ion source for medical applications. In this study we have tested simultaneous generation of protons and THz radiation from a thin-foil target. We use a Ti:sapphire laser system (J-KAREN) at JAEA. A laser beam is focused by an off-axis parabolic mirror at the thin-foil target. We observed the high-energy proton in the rear side of the target and THz radiation in the reflected direction. Next, high energy protons are observed by reducing the size of preformed plasma.

Journal Articles

Control of laser-accelerated proton beams by modifying the target density with ASE

Yogo, Akifumi; Kiriyama, Hiromitsu; Mori, Michiaki; Esirkepov, T. Z.; Ogura, Koichi; Sagisaka, Akito; Orimo, Satoshi; Nishiuchi, Mamiko; Pirozhkov, A. S.; Nagatomo, Hideo*; et al.

European Physical Journal D, 55(2), p.421 - 425, 2009/11

 Times Cited Count:3 Percentile:20.28(Optics)

We demonstrate the laser-ion acceleration from a near-critical density plasma, when amplified spontaneous emission (ASE) was used to convert a solid foil target into the lower-density target. In this work, a direct comparison is made by changing the ASE intensity by factor 3 in order to investigate the target density-dependency of the laser-ion acceleration. The beam direction of high-energy component is successfully controlled by modifying the target density. The near-critical density plasma can be a favorable target to control the beam direction to be dependent on its energy.

Journal Articles

Observation of UV harmonics from a thin-foil target in the high-intensity laser-driven proton generation

Sagisaka, Akito; Pirozhkov, A. S.; Ma, J.-L.; Mori, Michiaki; Yogo, Akifumi; Ogura, Koichi; Orimo, Satoshi; Nishiuchi, Mamiko; Kiriyama, Hiromitsu; Kanazawa, Shuhei; et al.

Journal of Plasma and Fusion Research SERIES, Vol.8, p.464 - 467, 2009/09

We measure the UV harmonics from a thin-foil target by changing the laser pulse duration in the high-energy proton generation. The maximum proton energies are around 1 MeV. In the case of the $$sim$$500 fs, the peaks of UV harmonics up to fourth-order clearly appear. The spectra are broadened and shifted at the pulse durations of $$sim$$100 fs and $$sim$$30 fs.

Journal Articles

Ion acceleration using temporally-controlled high-intensity laser pulses

Yogo, Akifumi; Daido, Hiroyuki; Mori, Michiaki; Kiriyama, Hiromitsu; Bulanov, S. V.; Bolton, P. R.; Esirkepov, T. Z.; Ogura, Koichi; Sagisaka, Akito; Orimo, Satoshi; et al.

Reza Kenkyu, 37(6), p.449 - 454, 2009/06

The acceleration of protons driven by a high-intensity laser is comprehensively investigated via control of the target density by using ASE just before the time of the main-laser interaction. Two cases were investigated for which the ASE intensity differed by three orders of magnitude: In the low contrast case the beam centre for higher energy protons is shifted closer to the laser-propagation direction of 45$$^{circ}$$, while the center of lower-energy beam remains near the target normal direction. Particle-in-cell simulations reveal that the characteristic proton acceleration is due to the quasistatic magnetic field on the target rear side with the magnetic pressure sustaining a charge separation electrostatic field.

Journal Articles

Modification of JRR-4; Remodeling of reactor building

; ; ; Nakajima, Teruo; Akutsu, Yoichi; ; Naruse, Hideo

UTNL-R-0378, p.6.1 - 6.9, 1999/00

no abstracts in English

JAEA Reports

None

Kano, Shigeki; Koakutsu, Toru; Hasegawa, Naruo; Nakayama, Koichi; Nakasuji, Takashi; Atsumo, Hideo

PNC TN941 77-111, 95 Pages, 1977/06

PNC-TN941-77-111.pdf:4.43MB

A corrosion test of hard facing material has been conducted in 600$$^{circ}$$C sodium for 2000 hrs. Test pieces were Co base alloys, Ni base alloys and carbides which were provided for tribology studies in sodium. These materials were compared with SUS304, SUS316 and another corrosion and heat resisting alloys by simultaneous exposure. Analysis methods after exposure were as follows: surface roughness, hardness, corrosion rate, surface morphology and metallurgical structure which have influence on friction and self-welding behavior. The results obtained are as follows: (1)Stellitew alloys: Part of test pieces showed weight gain. Change of surface roughness was minute. Structural change was not observed in the surface vicinity of sodium contact. However, hardness increase was observed. (2)Ni base hard facing materials such as Colmonoy alloys: Corrosion rates were high and hardness was reduced. A degraded layer of 10$$mu$$m through 40$$mu$$m was observed on the surface of Colmonoy alloys and their surface roughness increased. (3)Inconel alloys: Corrosion rates were double those of stainless steels. A degraded layer of 1$$mu$$m through 4$$mu$$m was observed on the surface. Change in surface roughness was minute. (4)Corrosion and heat resisting alloys: Corrosion rates showed one to two times greater than those of stainless steels. Change in surface roughness was minute. No change in surface layer was observed. However, precipitates were observed in the metallurgical structures of some alloy types. (5)Carbides: Large increase of surface roughness was observed. LC-1C exhibited stripping from substratum. LW-1N40 indicated wide variation in corrosion rates. (6)Other materials: SUS316 produced a sigma phase at the grain boundary of sodium surface contact.

JAEA Reports

In sodium tests of hard facing materials, 2; Test Result in room temperature argon

Kano, Shigeki; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Namekawa, Masaru; Nakasuji, Takashi; Atsumo, Hideo

PNC TN941 77-179TR, 48 Pages, 1977/01

PNC-TN941-77-179TR.pdf:2.29MB

JAEA Reports

In sodium tests of hard facing materials, 2; Test Result in room temperature argon

Kano, Shigeki; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Nakasuji, Takashi; Namekawa, Masaru; Atsumo, Hideo

PNC TN941 77-179, 48 Pages, 1977/01

PNC-TN941-77-179.pdf:2.55MB
PNC-TN941-77-179TR.pdf:2.29MB

A series of experiments have been carried out to develop and screen friction and wear resistant materials used for sliding components of a sodium cooled reactor. Preceding studies $$^{(1)-(5)}$$ clarified the short-term friction and wear characteristics of various materials in 450$$^{circ}$$C sodium. A present study relates to clarify friction and wear behavior in argon environment, where a part of sliding components are located, and compare test data in room temperature argon with those in 450do sodium. The results obtained are as follows: (1)Static friction coefficients ($$mu$$s) in argon were almost lower than 0.2. They were apt to be lower than those in sodium. (2)Kinetic friction coefficients ($$mu$$k) in argon varied with load. The difference of $$mu$$k in argon and sodium depended on material combination. (3)Wear rates were remarkably high in argon. Wear rates of Colmonoy and Stellite were not detected in sodium, but were detected in argon. (4)Sliding surface was more roughened in argon, and hardness of sliding surface was almost lower in argon than in sodium. (5)There is the significant difference between friction and wear characteristics argon and those in sodium. Then, it is difficult that in-sodium behavior is estimated with in-argon data. (6)The above-mentioned difference in room temperature argon and 450$$^{circ}$$C sodium will be greater when the test is carried out in higher temperature argon.

JAEA Reports

Wear tests of materials for FBR in sodium environment (V); Differences between Colmonoy and Stellite alloys

Kano, Shigeki; *; Nakayama, Koichi; Hasegawa, Naruo; Koakutsu, Toru; Atsumo, Hideo; Nakasuji, Takashi

PNC TN941 76-81, 25 Pages, 1976/07

PNC-TN941-76-81.pdf:0.88MB

A series of experiments in sodium environment have been carried out to develop and screen the friction and wear resistant materials used for sliding components of the sodium cooled reactor. The present study relates to the friction and wear characteristics of nickel-basealloy "Colmonoy" and cobalt-base alloy "Stellite" with respect to temperature, load, sliding velocity, sliding mode and sodium flushing. Also several experiments were carried out in argon and atmospheric environments, and they were compared with those in sodium. The results obtained were as follows : (1)As the sodium temperature is raised, the kinetic friction coefficient ($$mu$$$$_{k}$$) of Stellite alloy becomes higher, but that of colmonoy alloy remains constant or is rather lower. The $$mu$$$$_{k}$$ of Collmonoy alloy becomes lower by 540$$^{circ}$$C sodium flushing. (2)Both static friction coefficient ($$mu$$$$_{s}$$) and $$mu$$$$_{k}$$ of Colmonoy alloy are lower than those of Stellite alloy in sodium environment. (3)The dependence of $$mu$$$$_{s}$$ and $$mu$$$$_{k}$$ upon the load is low in sodium environment. In argon the dependence of $$mu$$$$_{s}$$ upon the load is not found, while $$mu$$$$_{k}$$ varies according to the load. (4)The friction behavior is influenced by sliding mode. The $$mu$$$$_{k}$$ in oscillating sliding is higher than that in one-directional continuous sliding. Also the sliding surface in oscillating sliding is more roughened. (5)The dependence of $$mu$$$$_{k}$$ upon the sliding velocity is not found in sodium environment except for that in low velocity area. (6)The kinetic friction coefficient is apt to be higher in argon than in sodium. Also the wear rate is much higher in argon.

JAEA Reports

Non-destructive assay equipment for quantitative determination of the nuclear material in plutonium fuel fabrication facility

; Akutsu, Hideo*; *; Miyahara, Kenji; *; *

PNC TN841 75-34, 23 Pages, 1975/09

PNC-TN841-75-34.pdf:0.41MB

Non-destructive assay equipment for quantitative determination of the neuclear material in plutonium fuel fabrication facility. In plutonium fuel Fabrication Facility (PFFF) of PNC, nuclear materials are received in the form of oxide powder both for plutonium and uranium as raw material, and are shipped to reactor site as the sub-assembly after passing through fabrication processes such as pellet preparation, fuel rod fabrication and assembling. This production line has some strategic points where the nondestructive assay is available for the safeguards techniques. In our facility, four strategic points for nondestructive assay were established as follows. (1) Receiving of nuclear material, (2) Shipping of subassembly, (3) Fuel rod, (4) Contaminated waste and scrap of the fuel power or pellets. This paper reports the result obtained from a callorimeter, $$gamma$$scanner, neutron coincidence meter that was prepared for these strategic points.

JAEA Reports

Potentiality of an accounting system for nuclear materials in the PNC plutonium fuel facilities

*; ; *; Akutsu, Hideo*

PNC TN841 75-33, 13 Pages, 1975/09

PNC-TN841-75-33.pdf:1.41MB

The accounting system based on filing of data and inquiry processingby the use of an optical mark reader (OMR) has been developed and operated satisfactorily for criticality control and accountancy of nuclear materialsin plutonium facilities of PNC. The OMR system has merits, especially compared with an old chit and punch card system, such as low cost, abundance of the data included on a single sheet, universality of use for all kinds of material transfers, easiness of data correction, and large capacity todeal with. The OMR system is applied to the material transfer and also for the physical inventory taking. This system, together with the use of an accurate automatic balance equipped at each glove box, which is generally designated as an accounting unit for the criticality control, generated a MUF of 0.43% for a fuel fabrication campaign of 119 assemblies for a fast reactor, which can be decreased further. In correspondence to the recent safe guarding situation and also to fitting to an automatic fuel fab

JAEA Reports

Screening test for duct pad materials of fuel assembly (I); Frictional coefficient in a sodium environment

Mizobuchi, Shotaro*; *; Koakutsu, Toru; Atsumo, Hideo

PNC TN941 75-55, 42 Pages, 1975/07

PNC-TN941-75-55.pdf:2.59MB

We have been conducted experiments to select for the contacting and sliding material use in F.B.R.. In present study, we tested in simulated condition for 6 kind of the candidated materials as duct pad of fuel assembly. The following results were obtained, (1)SUS316 showed a bad frictional behivor as the high frictional coefficient of 0.8, and hard chrome plating, also, have been unstable frictional behavior and become to the lower hardness after tested in 540$$^{circ}$$C sodium. (2)The brush-finished chrome carbide showed the more stable frictional behaivor than the grinder-finished material, and frictional coefficient showed approximately 0.5. This coefficient was independent on the temperature in this test. (3)Colmonoy No.6 indicated the lowest frictional coefficient of 0.34 in materials of present studys. But, stellite No.6 showed a little unstable friction behavior even if tested in 280$$^{circ}$$C sodium. (4)Each of tested materials were observed increasing frictional coefficient, after tested dwelling in 540$$^{circ}$$C sodium. It was recognized that colmonoy No.6 and the brush-finished chrome carbide seem to be the promising as duct pad materials.

JAEA Reports

Certificate and records of PNC fuel pins for RAPSODIE-5 irradiation program

Akutsu, Hideo*; Koizumi, Masumichi; Kashima, Sadamitsu; *

PNC TN841 75-15, 55 Pages, 1975/04

PNC-TN841-75-15.pdf:2.55MB

This document is completed according to the quality control and testing procedures described in "Preliminary Design of PNC-5 Subassembly for Rapsodie Irradiation" Coprecipilation methods was employed for preparing PuO$$_{2}$$-UO$$_{2}$$ powder. Five lots of pellets are provided for fablication of forty fuel pins. Fablication process of PuO$_{2-UO$_{2 powder, pellets and fuel pins are shown in Fig.3-1, Fig.3-2, Fig.3-3 respectively.

JAEA Reports

Irradiation performance test of PuO$$_{2}$$-UO$$_{2}$$ fuels by saxton reactor

Akutsu, Hideo*; *

PNC TN841 74-50, 58 Pages, 1974/12

PNC-TN841-74-50.pdf:6.93MB

Mixed oxide (PuO$$_{2}$$-UO$$_{2}$$) fuel rods (four rods and oneassembly containing 68 rods) were irradiated to certificate irradiation performance of proto-typed fuel by saxton reactor to peak burnups of up to 8,050 MWd/mtm. linear power level was from 200 to 500 watts/cm. after irradiation, post-irradiation examinations were conducted in battelle's columbus laboratories (BCL). The post irradiation examinations were consisted of visual examination, profilometry, gamma scanning, fuel and clad metallography, burnup analysis, hydride analysis in claddings and clad strength tests. These examinations showed that the overall performance of the PuO$$_{2}$$-UO$$_{2}$$ fuel was satisfactory.

JAEA Reports

Irradiation Performance Test of PuO$$_{2}$$-UO$$_{2}$$ Fuels by Saxton Reactor

Akutsu, Hideo*; Koizumi, Masumichi

PNC TN841 74-49, 53 Pages, 1974/12

PNC-TN841-74-49.pdf:2.61MB

Mixed oxide(PuO$$_{2}$$-UO$$_{2}$$) fuel rods (fourrods and one assembly containing 68 rods) were irradiated to certificate irradiationperformance of proto-typed fuel by SaxtonReactor to peak burnups of up to 80,500 MWD/MTM. Linear power level was from 200 to 500 watts/cm. After irradiation,post-irradiationexaminations were conducted in Battelle's Columbus Laboratories (BCL). The postirradiation examinations were consisted of visual examination, profilometry, gamma scanning, fuel and clad metallography, burnup analysis, hydride analysis in claddings and clad strength tests. These examinations showed that the overall performance of the PuO$$_{2}$$-UO$$_{2}$$ fuel was satisfactory.

JAEA Reports

Uraniumu-Plutoniumu Mixed-Oxide Fuel Fabrcation for the Deuterium Critical Assembly "DCA" in JAPAN

Akutsu, Hideo*; *; *; Naruki, Kaoru

PNC TN843 74-13, 36 Pages, 1974/11

PNC-TN843-74-13.pdf:0.7MB

The construction of the prototype heavywater reactor "FUGEN" is currentlyprogressing on the schedule to be criticalin 1976. Prior to this reactor operation,the reactor physics examination are carringout with the Deuterium Critical Assembly "DCA" since 1973. A new facility, thePlutonium Fuel Fabrication Facility (PFFF)of PNC which is mainly devoted to mass-production, was constructed to meet theplutonium fuel fabrication requirement forPNC's FBR and ATR projects. At the "ATR line" of this PFFF, thefabrication of the plutomium fuel elementsfor DCA had been carried out since Mar. 1972, and 92 fuel assemblies with the totalmixed-oxide amounting to as much as 10tons were completed in Feb. 1973. It was the first experience in Japanthat,such a large amounts of mixed-oxidewas fabricated as the fuel assembliescomposed of three kinds of fuel rodsaccording to both the isotopic charactor and the plutonium enrichment, totaling about2600 fuel rods.

JAEA Reports

None

Akutsu, Hideo*; *

PNC TN841 74-27, 174 Pages, 1974/08

PNC-TN841-74-27.pdf:14.81MB

no abstracts in English

JAEA Reports

None

*; Akutsu, Hideo*; *; ; Yumoto, Ryozo; *; Sasajima, Hideyoshi*; *

PNC TN841 74-13, 65 Pages, 1974/06

PNC-TN841-74-13.pdf:1.61MB

None

JAEA Reports

Safety analysis code system SAFE

Akutsu, Hideo*; Mizuta, H.

PNC TN843 74-02, 122 Pages, 1974/02

PNC-TN843-74-02.pdf:2.9MB

None

27 (Records 1-20 displayed on this page)