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Journal Articles

Development of FRENDY nuclear data processing code; Generation capability of multi-group cross sections from ACE file

Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi

Transactions of the American Nuclear Society, 122(1), p.714 - 717, 2020/06

A generation capability of multi-group cross sections from point-wise cross sections in ACE files is being developed as a function of the nuclear data processing code FRENDY. This presentation describes features of this function and comparison of the processing results between this function and GROUPR module in NJOY.

JAEA Reports

Fast reactor nuclear physics parameters calculation code system "EXPARAM"

Iijima, Susumu*; Kato, Yuichi*; Takasaki, Kenichi*; Okajima, Shigeaki

JAERI-Data/Code 2004-016, 91 Pages, 2004/12

JAERI-Data-Code-2004-016.pdf:7.45MB

The calculation code system "EXPARAM" was designed to analyze the experimental results systematically measured at the fast critical assembly (FCA). Some calculation codes developed independently in JAERI and in US research institutes were collected and arranged as the fast reactor physics calculation code system. The multi-group core calculation code and the perturbation calculation code based on the diffusion theory and the transport theory calculate the reactor physics parameters such as eigenvalue, reaction rate, Doppler reactivity worth and sodium void worth. The dynamic physics parameters such as prompt neutron lifetime and effective delayed neutron fraction are also calculated. Input and Output data of calculation codes are transferred to each other using a direct access file on UNIX computer system.

Journal Articles

Benchmark calculation for deep penetration problem of 14MeV neutrons in iron

Mori, Takamasa; Nakakawa, Masayuki

Journal of Nuclear Science and Technology, 29(11), p.1061 - 1073, 1992/11

no abstracts in English

JAEA Reports

JAEA Reports

One-, tow-, three-dimensional transport codes using multi-group double-differential form cross sections

Mori, Takamasa; Nakakawa, Masayuki; *

JAERI 1314, 151 Pages, 1988/11

JAERI-1314.pdf:4.5MB

no abstracts in English

JAEA Reports

ANISN-DD; One-dimensional Sn transport code using multi-group double-differential form cross sections

Mori, Takamasa; *; Nakakawa, Masayuki

JAERI-M 87-123, 55 Pages, 1987/08

JAERI-M-87-123.pdf:1.21MB

no abstracts in English

JAEA Reports

PROF-DD; A code system for generation of multi-group double-differential form cross section library

; Nakagawa, Masayuki;

JAERI-M 86-124, 57 Pages, 1986/08

JAERI-M-86-124.pdf:1.36MB

no abstracts in English

JAEA Reports

JAEA Reports

JSD 1000:Multi-Group Cross Section Sets for Shielding Materials

JAERI-M 84-038, 116 Pages, 1984/03

JAERI-M-84-038.pdf:3.34MB

no abstracts in English

Journal Articles

Development of the computer code system JACS for criticality safety

; ;

Transactions of the American Nuclear Society, 41, p.329 - 330, 1982/00

no abstracts in English

Oral presentation

Recent development of FRENDY

Tada, Kenichi

no journal, , 

This presentation explains the recent development work of the nuclear data processing code FRENDY. This presentation shows the major new functions in FRENDY version 2 which was released in Jan. 2022 and the overview of the new functions implemented in the revised version which was released in Nov. 2022.

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