R&D on Accelerator Driven Nuclear Transmutation System (ADS) at J-PARC, 2; Transmutation Experimental Facility at J-PARC

Maekawa, Fujio; Takei, Hayanori

Purazuma, Kaku Yugo Gakkai-Shi, 98(5), p.206 - 210, 2022/05

In developing an accelerator-driven nuclear transmutation system (ADS), it is necessary to solve technical issues related to proton beams, such as the development of materials that can withstand high-intensity proton beams and the characterization of subcritical cores driven by proton beams. Therefore, at the high-intensity proton accelerator facility J-PARC, a transmutation experimental facility that actually conducts various tests using a high-intensity proton beam is being planned. This paper introduces the outline and future direction of the transmutation experimental facility.

Natural convection heat transfer of high temperature gas in an annulus between two vertical concentric cylinders

Inaba, Yoshitomo; Zhang, Y.*; Takeda, Tetsuaki; Shiina, Yasuaki

Heat Transfer-Asian Research, 34(5), p.293 - 308, 2005/07

https://doi.org/10.1002/htj.20070

Water cooling panels have been adopted as the vessel cooling system of the HTTR to cool the reactor core indirectly by natural convection and thermal radiation. In order to investigate the heat transfer characteristics of high temperature gas in a vertical annular space between the reactor pressure vessel and cooling panels of the HTTR, we carried out experiments and numerical analyses on natural convection heat transfer coupled with thermal radiation heat transfer in an annulus between two vertical concentric cylinders with the inner cylinder heated and the outer cylinder cooled. In the present experiments, Rayleigh number based on the height of the annulus ranged from 2.010 to 5.410 for helium gas and from 1.210 to 3.510 for nitrogen gas. The numerical results were in good agreement with the experimental ones regarding the surface temperatures of the heating and cooling walls. As a result of the experiments and the numerical analyses, the heat transfer coefficient of natural convection coupled with thermal radiation was obtained.

Proceedings of the 11th International Workshop on Ceramic Breeder Blanket Interactions; December 15 - 17, 2003, Tokyo, Japan

Enoeda, Mikio

JAERI-Conf 2004-012, 237 Pages, 2004/07

JAERI-Conf-2004-012.pdf:44.1MB

This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of LiTiO and other breeders, fabrication technology developments and characterization of the LiTiO and LiSiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.

Study on the analyses of the reactor physics benchmark problem for the LWR next generation fuels

Research Committee on Reactor Physics

JAERI-Research 2004-004, 409 Pages, 2004/03

JAERI-Research-2004-004.pdf:28.53MB

This report summarizes the second phase (FY2001-2002) activity of "the Working Party (WP) on Reactor Physics for LWR Next Generation Fuels". The next generation fuels mean the ones aiming at further extended burn-up such as 70GWd/t over the current design. In the WP, the benchmark activity has been conducted to investigate and improve the calculation accuracy of the nuclear characteristics of the next generation fuels. In the second phase activity, all benchmark results were compiled and compared. Based on the comparison, the present status of calculation accuracy for the next generation fuels has been confirmed, and the factors causing the calculation differences were analyzed in detail. Moreover, analyses of the post irradiation and critical experiments with the codes used in the benchmark were reviewed, and future experiments and research subjects necessary to reduce the calculation differences were discussed and proposed.

Selected materials of the international workshop on radiation risk and its origin at molecular and cellular level; February 6-7, 2003

Pinak, M.

JAERI-Conf 2003-011, 113 Pages, 2003/09

JAERI-Conf-2003-011.pdf:10.08MB

The workshop "International Workshop on Radiation Risk and its Origin at Molecular and Cellular Level" was held at The Tokai Research Establishment, Japan Atomic Energy Research Institute, on the 6th and 7th of February 2003. The Laboratory of Radiation Risk Analysis of JAERI organized it. This international workshop attracted scientists from several different scientific areas, including radiation physics, radiation biology, molecular biology, crystallography of biomolecules, modeling and bio-informatics. Several foreign and domestic keynote speakers addresses the very fundamental areas of radiation risk and tried to establish a link between the fundamental studies at the molecular and cellular level and radiation damages at the organism. The symposium consisted of 13 oral lectures, 10 poster presentations and panel discussion. The 108 participants attended the workshop. This publication comprises of proceedings of oral and poster presentations where available. For the rest of contributions the abstracts or/and selections of presentation materials are shown instead.

Study on natural convection heat transfer in vertical annular space of a double coaxial cylinder

Inaba, Yoshitomo; Takeda, Tetsuaki

JAERI-Research 2000-062, 73 Pages, 2001/02

JAERI-Research-2000-062.pdf:2.83MB

no abstracts in English

Neutronic design of pulse operation simulating device for in-pile functional test of fusion blanket by MCNP

Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi

Journal of Nuclear Science and Technology, 37(Suppl.1), p.423 - 426, 2000/03

https://doi.org/10.1080/00223131.2000.10874920

no abstracts in English

Development of heat and radiation resistant optical fibers

Shikama, Tatsuo*; Ishihara, Masahiro; Hayashi, Kimio; Kakuta, Tsunemi; Shamoto, Naoki*; Ishino, Shiori*

Proceedings of 1st Information Exchange Meeting on Basic Studies on High-Temperature Engineering, p.379 - 386, 1999/09

no abstracts in English

Measurements of neutrons and photons Leaked through three-legs labyrinth from 68-MeV proton target room

; Nakane, Yoshihiro; Sakamoto, Yukio; Nakashima, Hiroshi; Meigo, Shinichiro; Tanaka, Shunichi; Kurosawa, Tadahiro*; Nakamura, Takashi*; Nakao, Noriaki*; Hirayama, Hideo*; et al.

Proc. of 1998 ANS Radiat. Protection and Shielding Division Topical Conf. Technol. for the New Century, 2, p.164 - 169, 1998/00

no abstracts in English

Preparation of functions of computer code GENGTC and improvement for two-dimensional heat transfer calculations for irradiation capsules

Nomura, Yasushi; ;

JAERI-M 92-163, 66 Pages, 1992/11

JAERI-M-92-163.pdf:1.75MB

no abstracts in English