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Journal Articles

The Development of a Multiphysics Coupled Solver for Studying the Effect of Dynamic Heterogeneous Configuration on Particulate Debris Bed Criticality and Cooling Characteristics

Li, C.-Y.; Wang, K.*; Uchibori, Akihiro; Okano, Yasushi; Pellegrini, M.*; Erkan, N.*; Takata, Takashi*; Okamoto, Koji*

Applied Sciences (Internet), 13(13), p.7705_1 - 7705_29, 2023/07

 Times Cited Count:1 Percentile:0(Chemistry, Multidisciplinary)

Journal Articles

GPU-acceleration of locally mesh allocated two phase flow solver for nuclear reactors

Onodera, Naoyuki; Idomura, Yasuhiro; Ali, Y.*; Yamashita, Susumu; Shimokawabe, Takashi*; Aoki, Takayuki*

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.210 - 215, 2020/10

This paper presents a GPU-based Poisson solver on a block-based adaptive mesh refinement (block-AMR) framework. The block-AMR method is essential for GPU computation and efficient description of the nuclear reactor. In this paper, we successfully implement a conjugate gradient method with a state-of-the-art multi-grid preconditioner (MG-CG) on the block-AMR framework. GPU kernel performance was measured on the GPU-based supercomputer TSUBAME3.0. The bandwidth of a vector-vector sum, a matrix-vector product, and a dot product in the CG kernel gave good performance at about 60% of the peak performance. In the MG kernel, the smoothers in a three-stage V-cycle MG method are implemented using a mixed precision RB-SOR method, which also gave good performance. For a large-scale Poisson problem with $$453.0 times 10^6$$ cells, the developed MG-CG method reduced the number of iterations to less than 30% and achieved $$times$$ 2.5 speedup compared with the original preconditioned CG method.

Journal Articles

Solomon; A Monte Carlo solver for criticality safety analysis

Nagaya, Yasunobu; Ueki, Taro; Tonoike, Kotaro

Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019) (Internet), 9 Pages, 2019/09

A new Monte Carlo solver Solomon has been developed for the application to fuel-debris systems. It is designed not only for usual criticality safety analysis but also for criticality calculations of damaged reactor core including fuel debris. This paper describes the current status of Solomon and demonstrates the applications of the randomized Weierstrass function (RWF) model and the RWF model superimposed voxel geometry.

JAEA Reports

Development of corrosion testing equipment to evaluate corrosion resistance in fuel dissolved solution (Contract research)

Motooka, Takafumi; Terakado, Shogo; Koya, Toshio; Kiuchi, Kiyoshi

JAERI-Tech 2001-089, 52 Pages, 2002/01

JAERI-Tech-2001-089.pdf:5.05MB

The safety for corrosion of various metals applied to spent fuel dissolvers has been evaluated by the mock-up tests using small scaled equipment and the reference tests in laboratories with small specimens. These tests have been conducted under un-radioactive environments. The environment in practical reprocessing plants has many radioactive species. Therefore, the effect of irradiation on corrosion should be evaluated in detail.In this study, the corrosion testing equipment employed to simulate environments in a dissolver has been developed. This report describes the specification of corrosion testing equipment and the results of primary and reference and hot tests.Corrosion test using the equipment under heat transfer and irradiation conditions have been carried out for 1000 hours in safety. As a result, it has been indicated that zirconium has excellent corrosion resistance in fuel dissolved solution. It is expectable that useful corrosion test data in radioactive environment are accumulated with this equipment in future.

Journal Articles

Toward an ultimate goal for universal solution by the CIP method

Yabe, Takashi*; Utsumi, Takayuki*

Computational Fluid Dynamics Journal, 9(3), p.185 - 193, 2000/10

no abstracts in English

Journal Articles

Development of treatment technology for carbon-14 in dissolver off-gas of spent fuel

Mineo, Hideaki; ; *; Uchiyama, Gunzo; Fujine, Sachio

Proc. of 7th Int. Conf. on Radioactive Waste Mamagement and Environmental Remediation (ICEM '99)(CD-ROM), 3 Pages, 1999/00

no abstracts in English

Journal Articles

Spent fuel test of an advanced PUREX process:PARC

Mineo, Hideaki; Uchiyama, Gunzo; Hotoku, Shinobu; Asakura, Toshihide; Kihara, Takehiro; *; ; Kimura, Shigeru; *; ; et al.

Proc. of Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 7 Pages, 1999/00

no abstracts in English

Journal Articles

Application of the differential algebraic-cubic interpolated propagation scheme to the heat conduction equations

*; Kunugi, Tomoaki

Computational Fluid Dynamics Journal, 4(3), p.265 - 277, 1995/10

no abstracts in English

JAEA Reports

Analyses with MCNP code of the criticality experiment of pellet-solution coexisting low-enriched uranium fuel

*; Arakawa, Takuya*; Okuno, Hiroshi

JAERI-Data/Code 94-018, 36 Pages, 1994/12

JAERI-Data-Code-94-018.pdf:1.09MB

no abstracts in English

JAEA Reports

Journal Articles

Plasma simulator METIS for tokamak confinement and heating studies

Takeda, Tatsuoki; Tani, Keiji; Tsunematsu, Toshihide; Kishimoto, Yasuaki; ; *; *

Parallel Computing, 18, p.743 - 765, 1992/00

 Times Cited Count:2 Percentile:48.33(Computer Science, Theory & Methods)

no abstracts in English

Journal Articles

Simulation of spent fuel dissolution in reprocessing

; Fujine, Sachio; Maeda, Mitsuru; Adachi, Takeo; Sakurai, Tsutomu; *

Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management,Vol. 2, p.682 - 686, 1991/00

no abstracts in English

Journal Articles

Does releasing of RuO$$_{4}$$ in to dissolver off gas occur?

; *

UTNL-R-0190, p.17 - 19, 1986/00

no abstracts in English

Oral presentation

Oral presentation

16 (Records 1-16 displayed on this page)
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