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Journal Articles

Measurement and analysis of reactivity worth of $$^{241}$$Am sample in water-moderated low-enriched UO$$_2$$ fuel lattices at TCA

Sakurai, Takeshi; Mori, Takamasa; Suzaki, Takenori*; Okajima, Shigeaki; Ando, Yoshihira*; Yamamoto, Toru*; Liem, P. H.*

Journal of Nuclear Science and Technology, 48(5), p.816 - 825, 2011/05

 Times Cited Count:2 Percentile:16.92(Nuclear Science & Technology)

JAEA Reports

Investigation on the JRR-3 high performance cold neutron source

Kumai, Toshio; Liem, P. H.*; Horiguchi, Yoji

JAERI-Tech 2002-023, 49 Pages, 2002/03

JAERI-Tech-2002-023.pdf:2.1MB

no abstracts in English

Oral presentation

Development of fundamental technologies of the Inverse-Planning System for Boron Neutron Capture Therapy

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Liem, P. H.*

no journal, , 

no abstracts in English

Oral presentation

Benchmark activity in Atomic Energy Society of Japan for improvement of reliability of nuclear fuel cycle simulators

Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Aizawa, Naoto*; Nakase, Masahiko*; Wada, Satoshi*; Wakasaki, Shingo*; Matsui, Minefumi*; Yasunaga, Yoshiaki*; Okamura, Tomohiro*; et al.

no journal, , 

This study presents benchmark activities conducted by a research committee of the Atomic Energy Society of Japan to enhance the reliability of nuclear fuel cycle simulators. Standard reactor libraries and phased benchmark scenarios were developed and applied to stepwise validation exercises. The results clarify consistency of simulators on burnup calculation and impact of human error. The results for 11 large-scale scenarios are also provided for future activity.

Oral presentation

Am-241 sample reactivity experiments in TCA, 2; Analysis of experimental cores and sensitivity analysis on Am-241 cross sections

Ando, Yoshihira*; Yamamoto, Toru*; Sakurai, Takeshi; Okajima, Shigeaki; Mori, Takamasa; Liem, P. H.*

no journal, , 

no abstracts in English

Oral presentation

Benchmarking of nuclear fuel cycle simulators in Atomic Energy Society of Japan

Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Aizawa, Naoto*; Nakase, Masahiko*; Wada, Satoshi*; Wakasaki, Shingo*; Matsui, Minefumi*; Yasunaga, Yoshiaki*; Okamura, Tomohiro*; et al.

no journal, , 

Nuclear fuel cycle simulators (NFCSs) are widely used but suffer from uncertainties and a lack of benchmarking for large, complex scenarios. To address this, the Atomic Energy Society of Japan established a committee to develop standard reactor libraries and benchmarking scenarios. Multiple Japanese NFCSs will analyze these scenarios, and the results will be published to improve NFCS reliability.

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