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Journal Articles

Evaluation of wall thinning of the steel piping after long term operation at Fugen Power Station

Ando, Ryosuke; Abe, Teruyoshi; Nakamura, Takahisa

E-Journal of Advanced Maintenance (Internet), 6(4), p.153 - 164, 2015/02

Wall thinning of serviced carbon steel piping of the secondary cooling system after long term operation of Advanced Thermal prototype Reactor (ATR) Fugen power station has been investigated as a series of evaluation of validity and availability of utilization of serviced materials on research projects focused on aging management. Reliability of wall thinning rates of the steel piping has been examined referring the previous inspection data. Examinations also have been made on prediction of wall thinning rates, rationalization of management of pipe wall thinning and verification of countermeasures against wall thinning.

Journal Articles

Research of estimation method of thermal aging embrittlement on cast austenitic stainless steel

Abe, Teruyoshi; Nogiwa, Kimihiro*; Onitsuka, Takashi*; Nakamura, Takahisa; Sakakibara, Yasuhide

E-Journal of Advanced Maintenance (Internet), 6(4), p.146 - 152, 2015/02

Thermal embrittlement of cast austenitic stainless steel components from the decommissioned advanced thermal prototype reactor Fugen has been characterized. Cast stainless steel materials were obtained from recirculation pump casing. The actual time at temperature for the materials was 138,000 h at 275$$^{circ}$$C. The "Fugen" material show modest decrease in Charpy-impact properties and a small increase in micro-Vickers hardness in ferrite phase because of thermal aging at relatively low service temperatures. The fracture toughness prediction method (H3T model) predicts slightly lower values for Charpy-impact energy obtained from the Fugen material. The results from microstructural analysis suggest that the prediction method have the potential to provide higher accuracy by considerations of the activation energy for embrittlement at low service temperatures.

Journal Articles

Basic technology development of advanced non-destructive detection / Measurement of nuclear material for nuclear security and nuclear nonproliferation

Seya, Michio; Naoi, Yosuke; Kobayashi, Naoki; Nakamura, Takahisa; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/01

The Integrated Support Center for Nuclear Non-proliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) has been conducting (based on collaborations with JAEA other centers) the following basic technology development programs of advanced non-destructive detection/measurement of nuclear material for nuclear security and nuclear non-proliferation. (1) The demonstration test of the Pu-NDA system for spent fuel assembly using PNAR and SINRD (JAEA/USDOE(LANL) collaboration, completed in JFY2013), (2) Basic development of NDA technologies using laser Compton scattered $$gamma$$-rays (Demonstration of an intense mono-energetic $$gamma$$-ray source), (3) Development of alternative to He-3 neutron detection technology, (4) Development of neutron resonance densitometry (JAEA/JRC collaboration)This paper introduces above programs.

Journal Articles

Influence of thermal aging on cast stainless steels used in JAEA's nuclear reactor Fugen

Nogiwa, Kimihiro; Onitsuka, Takashi; Abe, Teruyoshi; Sakakibara, Yasuhide; Horie, Kaoru; Nakamura, Takahisa

Journal of Nuclear Science and Technology, 50(9), p.883 - 890, 2013/09

 Times Cited Count:2 Percentile:77.96(Nuclear Science & Technology)

The degree of influence of thermal aging on cast stainless steels over a protracted time at low temperatures was investigated by means of a toughness test and microstructural characterization performed on components dismantled from the advanced thermal proto-type reactor "Fugen". The thermal embrittlement mechanism was examined using data obtained dismantled from the materials that had aged on site. The results of a Charpy impact test and microstructural characterization performed using 3DAP analysis reveal early signs of a thermal aging effect over a protracted period at low temperatures corresponding boiling-water reactor (BWR).

Journal Articles

Rehearsal and actual measurement of Fugen spent fuel assemblies by integrated PNAR and SINRD under the JAEA-USDOE collaboration program

Hayashi, Kenta; Nakamura, Takahisa; Takagi, Hisatsugu; Horie, Kaoru; Nakayama, Tamotsu; Hashimoto, Kazuhiko; Hayashi, Shoichi; Nakamura, Shinji; Takenaka, Shigeki; Ishizuka, Nobuo; et al.

Proceedings of INMM 54th Annual Meeting (CD-ROM), 10 Pages, 2013/07

JAEA and USDOE (Los Alamos National Laboratory (LANL)) have been collaborating on spent fuel measurements with a PNAR/SINRD NDA instrument at Fugen, in the course of the NGSI Spent Fuel Nondestructive Assay Project. In this collaboration, LANL's role has been to design and fabricate the detector (integrated PNAR and SINRD system), while JAEA's role has been to undertake the installation of the detector at the appropriate position in the spent fuel pool and to prepare for the actual measurements. In this paper we report the rehearsal of the measurement using a mock-up detector and a dummy fuel assembly in December 2012 and the plan of actual measurements in June 2013 (at the time of submission of this paper).

Journal Articles

Preparation for Pu measurement test of Fugen spent fuel assemblies by integrated PNAR/SINRD

Katano, Yoshiaki; Ebara, Noriyasu; Takagi, Hisatsugu; Nakamura, Takahisa; Bolind, A.; Seya, Michio

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10

The ATR, "Fugen" was a prototype nuclear reactor moderated by heavy water but cooled by boiling light water. It terminated its operations in 2003 and is now being decommissioned. Nevertheless, the spent-fuel pool at Fugen still remains and currently contains both MOX spent-fuel assemblies, and it is flexible enough to be able to conduct Non Destructive Assays (NDA) experiments on the spent fuel assemblies. Therefore, JAEA and the U.S. Los Alamos National Laboratory (LANL) are planning to conduct a test of an integrated PNAR/SINRD NDA measurement system at Fugen in 2013. LANL is designing and constructing the system, and JAEA is preparing the Fugen site for the test. The total experience of preparing for and conducting NDA measurements on actual spent fuel assemblies will teach important lessons about the practicality of applying such measurements in the future to spent fuel assemblies from commercial LWR power plants, especially with regard to satisfying legal and safety requirements.

Journal Articles

JAEA development programs of advanced technologies for safeguards and security

Bolind, A.; Kureta, Masatoshi; Soyama, Kazuhiko; Hajima, Ryoichi; Harada, Hideo; Nakamura, Takahisa; Seya, Michio

Kaku Busshitsu Kanri Gakkai (INMM) Nippon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10

JAEA has made progress in four development programs of advanced technologies for the measurement of nuclear material for safeguards and security. In the first program, we have designed and simulated a non-destructive assay (NDA) system that uses ZnS-ceramic-scintillator neutron detectors, instead of $$^{3}$$He neutron detectors. The second program is a basic demonstration of nuclear resonance fluorescence (NRF) as an NDA technique for measuring the fissile isotopes in nuclear material. Construction of one loop of an energy-recovery linac (ERL) at KEK in Tsukuba was begun this past year, and will finish in this fiscal year. The ERL will produce a high-intensity, mono-energetic $$gamma$$-ray beam for NRF. Also JAEA and the US Department of Energy are evaluating NRF-simulation codes. In the third program, we have started to design and construct a prototype of a new NDA system to determine the quantity of nuclear material in particle debris of melted nuclear fuel. It uses both neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). In the fourth program, we have made detailed preparations for testing a new NDA instrument (constructed by Los Alamos National Laboratory) on used nuclear fuel assemblies in the spent fuel pool at Fugen, next year. It uses a combined technique of passive neutron albedo reactivity (PNAR) and self-interrogation neutron resonance densitometry (SINRD).

Journal Articles

The JAEA part of the joint JAEA-U.S. DOE project for Pu measurement of Fugen spent fuel assemblies by integrated PNAR and SINRD

Ebara, Noriyasu; Katano, Yoshiaki; Nakamura, Takahisa; Takagi, Hisatsugu; Bolind, A.; Seya, Michio

Proceedings of INMM 53rd Annual Meeting (CD-ROM), 10 Pages, 2012/07

The Fugen advanced thermal reactor stopped operations in 2003 and is now being decommissioned. Nevertheless, the spent-fuel pool at Fugen still remains and currently contains both MOX and UO$$_{2}$$ spent-fuel assemblies. Because Fugen was a prototype, the standard operations at the spent-fuel pool are flexible enough to be able to conduct NDA experiments on the spent fuel. Therefore, JAEA and the U.S.DOE are planning to conduct a test of an integrated PNAR and SINRD NDA measurement system at Fugen in 2013. LANL is designing and constructing the detector, and JAEA is preparing the Fugen site for the test. It will be report to select for install location of NDA test device in spent fuel pool, how to installation and study of test flow.

Journal Articles

JAEA development programs of advanced technologies for safeguards and security

Bolind, A.; Kureta, Masatoshi; Soyama, Kazuhiko; Hajima, Ryoichi; Harada, Hideo; Nakamura, Takahisa; Seya, Michio

Proceedings of INMM 53rd Annual Meeting (CD-ROM), 10 Pages, 2012/07

This paper reports the progress that has been made at JAEA concerning 4 development programs of advanced technologies for the measurement of nuclear material for safeguards and security. One program is developing a neutron detector based on a ZnS ceramic scintillator material, to replace $$^{3}$$He neutron detectors. The other 3 programs are developing new non-destructive assay (NDA) systems. One system measures the nuclear resonance fluorescence (NRF) induced in fissile material by a high-intensity, mono-energetic $$gamma$$ ray beam, produced by a Laser Compton Scattering (LCS) system in an energy-recovery linac (ERL). Another system uses both neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA) to determine the fissile content in particle debris of melted nuclear fuel. The last system is a neutron-based, spent-fuel, NDA system that is being developed at Los Alamos National Laboratory (LANL). The system uses combines the techniques of self-interrogation neutron resonance densitometry (SINRD) and passive neutron albedo reactivity (PNAR). It will be tested on used nuclear fuel assemblies in the spent fuel pool at Fugen.

JAEA Reports

Conceptual design of the SlimCS fusion DEMO reactor

Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.

JAEA-Research 2010-019, 194 Pages, 2010/08

JAEA-Research-2010-019-01.pdf:48.47MB
JAEA-Research-2010-019-02.pdf:19.4MB

This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m$$^{2}$$. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

 Times Cited Count:124 Percentile:1.71(Physics, Fluids & Plasmas)

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m$$^{2}$$ or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

Journal Articles

Progress in the ITER physics basis, 3; MHD stability, operational limits and disruptions

Hender, T. C.*; Wesley, J. C.*; Bialek, J.*; Bondeson, A.*; Boozer, A. H.*; Buttery, R. J.*; Garofalo, A.*; Goodman, T. P.*; Granetz, R. S.*; Gribov, Y.*; et al.

Nuclear Fusion, 47(6), p.S128 - S202, 2007/06

 Times Cited Count:718 Percentile:3.51(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Effects of heavy-ion, UV-C, and X-ray irradiation on the susceptibilities of human cells to HIV-1 infection

Shimizu, Nobuaki*; Oue, Atsushi*; Otsuki, Takahiro*; Mori, Takahisa*; Yamaguchi, Kayo*; Nakamura, Takako*; Wada, Seiichi*; Kobayashi, Yasuhiko; Hoshino, Hiroo*

JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 105, 2007/02

Journal Articles

Report on ITPA (International Tokamak Physics Activity) meeting, 18

Kawahata, Kazuo*; Kawano, Yasunori; Kusama, Yoshinori; Mase, Atsushi*; Sasao, Mamiko*; Sugie, Tatsuo; Fujita, Takaaki; Fukuda, Takeshi*; Fukuyama, Atsushi*; Sakamoto, Yoshiteru; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 83(2), p.195 - 198, 2007/02

no abstracts in English

Journal Articles

A Simulation study on inductive ITB control in reversed shear tokamak discharges

Nakamura, Yukiharu; Tobita, Kenji; Fukuyama, Atsushi*; Takei, Nahoko; Takase, Yuichi*; Ozeki, Takahisa; Jardin, S. C.*

Nuclear Fusion, 46(8), p.S645 - S651, 2006/08

 Times Cited Count:3 Percentile:88.02(Physics, Fluids & Plasmas)

A self-consistent simulation, including a model for improved core energy confinement, demonstrates that externally applied, inductive current perturbations can be used to control both the location and strength of internal transport barriers (ITBs) in a fully non-inductive tokamak discharge. We find that ITB structures formed with broad non-inductive current sources such as LHCD are more readily controlled than those formed by localized sources such as ECCD. Through this external control of the magnetic shear profile, we can maintain the ITB strength which is otherwise prone to deteriorate when the bootstrap current increases.

Journal Articles

Report of ITPA (International Tokamak Physics Activity) meetings, 17

Asakura, Nobuyuki; Kato, Takako*; Nakano, Tomohide; Takamura, Shuichi*; Tanabe, Tetsuo*; Iio, Shunji*; Nakajima, Noriyoshi*; Ono, Yasushi*; Ozeki, Takahisa; Takechi, Manabu; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 82(7), p.448 - 450, 2006/07

no abstracts in English

Journal Articles

Numerical simulation on current spike behaviour of JT-60U disruptive plasmas

Takei, Nahoko; Nakamura, Yukiharu; Tsutsui, Hiroaki*; Yoshino, Ryuji; Kawano, Yasunori; Ozeki, Takahisa; Tobita, Kenji; Iio, Shunji*; Shimada, Ryuichi*; Jardin, S. C.*

Plasma Physics and Controlled Fusion, 46(12), p.1815 - 1830, 2004/12

 Times Cited Count:1 Percentile:96.82(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Alpha particle loss and neutral beam current drive in fusion plasma with central current hole

Tobita, Kenji; Ozeki, Takahisa; Nakamura, Yukiharu

Plasma Physics and Controlled Fusion, 46(7), p.S95 - S105, 2004/07

 Times Cited Count:10 Percentile:65.34(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Formation of advanced tokamak plasmas without the use of an ohmic-heating solenoid

Shiraiwa, Shunichi*; Ide, Shunsuke; Ito, Satoshi*; Mitarai, Osamu*; Naito, Osamu; Ozeki, Takahisa; Sakamoto, Yoshiteru; Suzuki, Takahiro; Takase, Yuichi*; Tanaka, Shigetoshi*; et al.

Physical Review Letters, 92(3), p.035001_1 - 035001_4, 2004/01

 Times Cited Count:42 Percentile:17.06(Physics, Multidisciplinary)

no abstracts in English

Journal Articles

TSC simulation of ITB crash and following disruption dynamics on JT-60U high-$$beta$$ reversed shear plasmas

Takei, Nahoko; Nakamura, Yukiharu; Kawano, Yasunori; Tsutsui, Hiroaki*; Ozeki, Takahisa; Tobita, Kenji; Sugihara, Masayoshi; Iio, Shunji*; Shimada, Ryuichi*; Jardin, S. C.*

Europhysics Conference Abstracts, 28G, 4 Pages, 2004/00

no abstracts in English

43 (Records 1-20 displayed on this page)