INVESTIGATION OF APPROPRIATE LADDER NUMBER ON PROBABILITY TABLE GENERATION von Tada, Kenichi

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Development and verification of a new nuclear data processing system FRENDY von Tada, Kenichi, Nagaya, Yasunobu, Kunieda, Satoshi, Suyama, Kenya, Fukahori, Tokio

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Application of the extended bias factor method for highly reliable benchmark suite von Tokashiki, Mikio, Ikehara, Tadashi, Tada, Kenichi, Egawa, Tohru, Yokoyama, Kenji, Iwamoto, Osamu

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Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region von Tada, Kenichi, Endo, Tomohiro

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General-purpose Nuclear Data Library JENDL-5 and to the Next von Iwamoto, Osamu, Iwamoto, Nobuyuki, Kunieda, Satoshi, Minato, Futoshi, Nakayama, Shinsuke, Kimura, Atsushi, Nakamura, Shoji, Endo, Shunsuke, Nagaya, Yasunobu, Tada, Kenichi, Konno, Chikara, Matsuda, Norihiro, Yokoyama, Kenji, Taninaka, Hiroshi, Oizumi, Akito, Okita, Shoichiro

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Statistical Uncertainty Quantification of Probability Tables for Unresolved Resonance Cross Sections von Tada, Kenichi, Endo, Tomohiro

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Important comments on KERMA factors and DPA cross-section data in ACE files of JENDL-4.0, JEFF-3.2 and ENDF/B-VII.1 von Konno, Chikara, Tada, Kenichi, Kwon, Saerom, Ohta, Masayuki, Sato, Satoshi

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FRENDY: A new nuclear data processing system being developed at JAEA von Tada, Kenichi, Nagaya, Yasunobu, Kunieda, Satoshi, Suyama, Kenya, Fukahori, Tokio

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ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations von Chiba, Go, Yamamoto, Akio, Tada, Kenichi

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An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis von Fujita, Tatsuya, Tada, Kenichi, Endo, Tomohiro, Yamamoto, Akio, Kosaka, Shinya, Hirano, Go, Nozaki, Kenichiro

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Adaptive setting of background cross sections for generation of effective multi-group cross sections in FRENDY nuclear data processing code von Yamamoto, Akio, Endo, Tomohiro, Tada, Kenichi

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Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition von Watanabe, Tomoaki, Tada, Kenichi, Endo, Tomohiro, Yamamoto, Akio

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Development of ACE file perturbation tool using FRENDY von Tada, Kenichi, Kondo, Ryoichi, Endo, Tomohiro, Yamamoto, Akio

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Multi-group neutron cross section generation capability for FRENDY nuclear data processing code von Yamamoto, Akio, Tada, Kenichi, Chiba, Go, Endo, Tomohiro

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Japanese evaluated nuclear data library version 5: JENDL-5 von Iwamoto, Osamu, Iwamoto, Nobuyuki, Kunieda, Satoshi, Minato, Futoshi, Nakayama, Shinsuke, Abe, Yutaka, Tsubakihara, Kohsuke, Okumura, Shin, Ishizuka, Chikako, Yoshida, Tadashi, Chiba, Satoshi, Otuka, Naohiko, Sublet, Jean-Christophe, Iwamoto, Hiroki, Yamamoto, Kazuyoshi, Nagaya, Yasunobu, Tada, Kenichi, Konno, Chikara, Matsuda, Norihiro, Yokoyama, Kenji, Taninaka, Hiroshi, Oizumi, Akito, Fukushima, Masahiro, Okita, Shoichiro, Chiba, Go, Sato, Satoshi, Ohta, Masayuki, Kwon, Saerom

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Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations von TADA, Kenichi, FUJITA, Tatsuya, ENDO, Tomohiro, YAMAMOTO, Akio, KOSAKA, Shinya, HIRANO, Go, NOZAKI, Kenichiro

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Evaluation of uranium-233 neutron capture cross section in keV region von Otuka, Naohiko, Tada, Kenichi, Cabellos, Oscar, Iwamoto, Osamu

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Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments von Fujimoto, Nozomu, Tada, Kenichi, Quan Ho, Hai, Hamamoto, Shimpei, Nagasumi, Satoru, Ishitsuka, Etsuo

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Applicability of the Diffusion and Simplified P3 Theories for Pin-by-Pin Geometry of BWR von TADA, Kenichi, YAMAMOTO, Akio, YAMANE, Yoshihiro, KITAMURAY, Yasunori

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Analyses of used BWR fuel assay data with the integrated burnup code system SWAT4.0 von Tada, Kenichi, Kikuchi, Takeo, Sakino, Takao, Suyama, Kenya

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