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Journal Articles

Implementation of a low-activation Au-In-Cd decoupler into the J-PARC 1 MW short pulsed spallation neutron source

Teshigawara, Makoto; Ikeda, Yujiro; Oi, Motoki; Harada, Masahide; Takada, Hiroshi; Kakishiro, Masanori*; Noguchi, Gaku*; Shimada, Tsubasa*; Seita, Kyoichi*; Murashima, Daisuke*; et al.

Nuclear Materials and Energy (Internet), 14, p.14 - 21, 2018/01

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

We developed an Au-In-Cd (AuIC) decoupler material to reduce induced radioactivity instead of Ag-In-Cd one, which has a cut off energy of 1eV. In order to implement it into an actual moderator-reflector assembly, a number of critical engineering issues need to be resolved with regard to large-sized bonding between AuIC and A5083 alloys by the hot isostatic pressing process. We investigated this process in terms of the surface conditions, sizes, and heat capacities of large AuIC alloys. We also show a successful implementation of an AuIC decoupler into a reflector assembly, resulting in a remarkable reduction of radioactivity by AuIC compared to AIC without sacrificing neutronic performance.

JAEA Reports

Thermal design study of lead-bismuth cooled accelerator driven system, 1; Study on thermal hydraulic behavior under normal operation condition

Akimoto, Hajime; Sugawara, Takanori

JAEA-Data/Code 2016-008, 87 Pages, 2016/09

JAEA-Data-Code-2016-008.pdf:15.62MB

Thermal hydraulic behavior in a lead-bismuth cooled accelerator driven system (ADS) is analyzed under normal operation condition. Input data for the ADS version of J-TRAC code have been constructed to integrate the conceptual design. The core part of the ADS is modeled in detail to evaluate the core radial power profile effect on the core cooling. As the result of the analyses, the followings are found; (1) Both maximum clad temperature and fuel temperature are below the design limits. (2) The radial power profile has little effect on the coolant flow distribution among fuel assemblies. (3) The radial power profile has little effect on the heat transfer coefficients along fuel rods. (4) The thermal hydraulic behaviors along four steam generators are identical. The thermal hydraulic behaviors along two pumps are also identical. A fast running input data is developed by the simplification of the detailed input data based on the findings mentioned above.

Journal Articles

ROSA/LSTF tests and RELAP5 posttest analyses for PWR safety system using steam generator secondary-side depressurization against effects of release of nitrogen gas dissolved in accumulator water

Takeda, Takeshi; Onuki, Akira*; Kanamori, Daisuke*; Otsu, Iwao

Science and Technology of Nuclear Installations, 2016, p.7481793_1 - 7481793_15, 2016/00

AA2016-0048.pdf:5.15MB

 Times Cited Count:1 Percentile:10.6(Nuclear Science & Technology)

JAEA Reports

Development of thermal-hydraulic design code for transmutation system with lead-bismuth cooled accelerator driven reactor

Akimoto, Hajime

JAEA-Data/Code 2014-031, 75 Pages, 2015/03

JAEA-Data-Code-2014-031.pdf:37.23MB

A thermal-hydraulic analysis code for transmutation system with lead-bismuth cooled accelerator-driven system (ADS) has been developed using the Japanese-version of Transient Reactor Analysis Code (J-TRAC) as the framework to apply the design studies of ADS. To identify the required capabilities of the thermal-hydraulic analysis code for ADS, previous thermal-hydraulic analyses of light water reactors, sodium-cooled fast reactor and ADS have been surveyed. To make up for insufficient capabilities of the J-TRAC code as a thermal-hydraulic analysis code of ADS, physical properties of lead-bismuth eutectic (LBE), argon gas and nitride nuclear fuel were implemented to the J-TRAC code. It was confirmed that the implemented capabilities worked as expected through verification calculations on (1) single-phase LBE flow, (2) heat transfer in a fuel assembly, and (3) heat transfer in a steam generator.

JAEA Reports

Proceedings of the 3rd Workshop on Dosimetry for External Radiations; November 28-29, 2002, Japan Atomic Energy Research Institute, Tokai, Ibaraki, Japan

Yoshizawa, Michio; Endo, Akira

JAERI-Conf 2003-002, 166 Pages, 2003/03

JAERI-Conf-2003-002.pdf:9.79MB

The present report is Proceedings of the Third Workshop on Dosimetry for External Radiations, held at the Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), in November 28-29, 2002. The proceedings comprises 16 papers and a summary of general discussion. The Third Workshop, subtitled "On an opportunity of the completion of the facility of calibration standards for neutron at JAERI", focused on neutron dosimetry and included presentations on the status of international neutron standards, the development of calibration techniques of neutron dosimeters using accelerator neutron sources, and dosimetry for high-energy neutrons. The workshop identified the directions for the future research and development in this field.

Journal Articles

Nuclear data relevant to accelerator driven system

Ikeda, Yujiro

Journal of Nuclear Science and Technology, 39(Suppl.2), p.13 - 18, 2002/08

no abstracts in English

JAEA Reports

Dose conversion coefficients in the shielding design calculation for high energy proton accelerator facilities

Sakamoto, Yukio; Yamaguchi, Yasuhiro

JAERI-Tech 2001-042, 29 Pages, 2001/06

JAERI-Tech-2001-042.pdf:1.79MB

no abstracts in English

Journal Articles

The IRAC code system to calculate activation and transmutation in the TIARA Facility

Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Hosono, Masakazu; Watanabe, Hiromasa; Yamano, Naoki*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.840 - 844, 2000/03

no abstracts in English

JAEA Reports

IRACM: A Code system to calculate induced radioactivity produced by ions and neutrons

; Fukuda, Mitsuhiro; ; Watanabe, Hiromasa; Yamano, Naoki*

JAERI-Data/Code 97-019, 91 Pages, 1997/05

JAERI-Data-Code-97-019.pdf:2.58MB

no abstracts in English

JAEA Reports

Neutron transmission benchmark problems of iron and concrete shields in low, intermediate and high energy proton accelerator facilities

Nakane, Yoshihiro; *; Sakamoto, Yukio; Yoshizawa, Nobuaki*; Nakao, Noriaki*; Ban, Shuichi*; Hirayama, Hideo*; *; Shin, Kazuo*; Nakamura, Takashi*

JAERI-Data/Code 96-029, 80 Pages, 1996/09

JAERI-Data-Code-96-029.pdf:2.34MB

no abstracts in English

Journal Articles

Development of the code system ACCEL for accelerator based transmutation research

; Sasa, Toshinobu; Takada, Hiroshi; Takizuka, Takakazu

Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.668 - 674, 1996/00

no abstracts in English

JAEA Reports

Benchmark problems for intermediate and high energy accelerator shielding

; Sakamoto, Yukio; Tanaka, Shunichi; ; Fukahori, Tokio; ; Sasamoto, Nobuo; Tanaka, Susumu; Nakamura, Takashi*; Shin, Kazuo*; et al.

JAERI-Data/Code 94-012, 90 Pages, 1994/09

JAERI-Data-Code-94-012.pdf:2.26MB

no abstracts in English

Journal Articles

Accelerator-based transmutation

Dai-26-Kai Robutsuri Kaki Semina, Tekisuto; Shometsu Shori Kenkyu, 0, p.47 - 66, 1994/00

no abstracts in English

JAEA Reports

QAD-SOR; An Interactive shielding calculation code for high energy electron accelerators

Sasamoto, Nobuo; *

JAERI-M 90-229, 61 Pages, 1991/01

JAERI-M-90-229.pdf:1.29MB

no abstracts in English

Journal Articles

Cathare analysis of natural circulation under normal and degraded secondary cooling conditions in LSTF RUNs ST-NC-06 and ST-NC-07

F.Serre*; Yonomoto, Taisuke; Kukita, Yutaka; *

EUROTHERM Seminar,No. 16; Natural Circulation in Industrial Applications, p.103 - 110, 1990/10

no abstracts in English

JAEA Reports

JAEA Reports

Vectorization of MHD Equilibrium and Stability Codes

Nemoto, Toshiyuki; Tsunematsu, Toshihide

JAERI-M 87-062, 36 Pages, 1987/04

JAERI-M-87-062.pdf:0.79MB

no abstracts in English

JAEA Reports

Positional Instability Analysis of Tokamak Plasmas by ERATO

; Tsunematsu, Toshihide; ; Takeda, Tatsuoki

JAERI-M 83-085, 26 Pages, 1983/06

JAERI-M-83-085.pdf:0.75MB

no abstracts in English

JAEA Reports

Forced Circulation Type Steam Generation Simulation Code:HT4

;

JAERI-M 82-106, 55 Pages, 1982/08

JAERI-M-82-106.pdf:1.07MB

no abstracts in English

JAEA Reports

Beta-Limit of a Large Tokamak with a Circular Cross Section

Tsunematsu, Toshihide; Takeda, Tatsuoki; ; ; *; R.Gruber*; F.Troyon*

JAERI-M 9890, 16 Pages, 1982/01

JAERI-M-9890.pdf:0.37MB

no abstracts in English

25 (Records 1-20 displayed on this page)