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Journal Articles

Report on the IAEA Technical Meeting "Nuclear Data Processing"

Tada, Kenichi

Kaku Deta Nyusu (Internet), (122), p.9 - 21, 2019/02

This paper reports the overview of the technical meeting of nuclear data processing in IAEA to Japanese researchers. In this technical meeting, the current status of nuclear data processing codes and verification of them are described.

Journal Articles

Development of next generation nuclear data processing code FRENDY

Tada, Kenichi

Robutsuri No Kenkyu (Internet), (71), 13 Pages, 2019/02

The nuclear data processing is very important to connect between the evaluated nuclear data library and the particle transport calculation code. However, many nuclear engineers do not know well about the nuclear data processing. This paper describes the overview of nuclear data processing and our nuclear data processing code FRENDY. This paper also lists references about the nuclear data processing.

JAEA Reports

Nuclear data processing code FRENDY version 1

Tada, Kenichi; Kunieda, Satoshi; Nagaya, Yasunobu

JAEA-Data/Code 2018-014, 106 Pages, 2019/01

JAEA-Data-Code-2018-014.pdf:1.76MB
JAEA-Data-Code-2018-014-appendix(DVD-ROM).zip:6.99MB

A new nuclear data processing code FRENDY has been developed in order to process the evaluated nuclear data library JENDL. Development of FRENDY helps to disseminate JENDL and various nuclear calculation codes. FRENDY is developed not only to process the evaluated nuclear data file but also to implement the FRENDY functions to other calculation codes. Users can easily use many functions e.g., read, write, and process the evaluated nuclear data file, in their own codes when they implement the classes of FRENDY to their codes. FRENDY is coded with considering maintainability, modularity, portability and flexibility. The processing method of FRENDY is similar to that of NJOY. The current version of FRENDY treats the ENDF-6 format and generates the ACE file which is used for the continuous energy Monte Carlo codes such as PHITS and MCNP. This report describes the nuclear data processing methods and input instructions for FRENDY.

Journal Articles

Improvement of probability table generation using ladder method for a new nuclear data processing system FRENDY

Tada, Kenichi

Proceedings of Reactor Physics Paving the Way Towards More Efficient Systems (PHYSOR 2018) (USB Flash Drive), p.2929 - 2939, 2018/04

JAEA develops a new nuclear data processing system FRENDY. We investigated all processing methods and we focused on the probability table generation using the ladder method which is adopted in the PURR module in NJOY. To improve the probability table generation, the more sophisticated method was introduced in the calculation methods of the Chi-Squared random numbers and the complex error function. We also investigated the appropriate ladder number. To investigate the impact of the difference of the complex error function calculation method, the K$$_{rm eff}$$ values of the benchmark experiments with the probability tables by the both methods were compared. The calculation results indicated that the appropriate ladder number is 100 and the difference of the calculation methods of the Chi-Squared random numbers and the complex error function has no significant impact on the neutronics calculation.

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 6; Processing and validation of nuclear data

Tada, Kenichi; Kosako, Kazuaki*; Yokoyama, Kenji; Konno, Chikara

Nippon Genshiryoku Gakkai-Shi, 60(3), p.168 - 172, 2018/03

The neutronics calculation codes cannot treat the evaluated nuclear data file directly. The nuclear data processing is required to use the nuclear data file in the neutronics calculation codes. The nuclear data processing is not just a converter but also many processes to evaluate the physical values for the neutronics calculation codes. In this paper, we describe the overview of the nuclear data processing and validation of the nuclear data.

Journal Articles

Development and verification of a new nuclear data processing system FRENDY

Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

Journal of Nuclear Science and Technology, 54(7), p.806 - 817, 2017/07

AA2016-0417.pdf:1.93MB

 Times Cited Count:3 Percentile:27.27(Nuclear Science & Technology)

JAEA has developed an evaluated nuclear data library JENDL and several nuclear analysis codes such as MARBLE2, SRAC, MVP and PHITS. Though JENDL and these computer codes have been widely used in many countries, the nuclear data processing system to generate the data library for application programs had not been developed in Japan and foreign nuclear data processing systems, e.g., NJOY and PREPRO are used. To process the new library for JAEA's computer codes immediately and independently, JAEA started to develop the new nuclear data processing system FRENDY in 2013. In this paper, outline, function, and verification of FRENDY are described.

Journal Articles

Report on the IAEC Consultants Meeting "The New Evaluated Nuclear Data File Processing Capabilities"

Tada, Kenichi

Kaku Deta Nyusu (Internet), (113), p.7 - 23, 2016/02

This paper reports the IAEA's Consultants Meeting (CM) in Oct. 5-9, 2015. The title of the CM is "The New Evaluated Nuclear Data File Processing Capabilities".

Journal Articles

Development of nuclear data processing code FRENDY

Tada, Kenichi

Kaku Deta Nyusu (Internet), (113), p.41 - 45, 2016/02

Author prized the incentive award for nuclear data division, Atomic Energy Society of Japan in 2015. This report introduces the overview of the award-winning work.

Oral presentation

Development of nuclear data processing system FRENDY, 2; Scattering cross section generation in the thermal energy range

Tada, Kenichi; Nagaya, Yasunobu

no journal, , 

JAEA has been developed the nuclear data processing system FRENDY (FRom Evaluated Nuclear Data librarY to any application). In this presentation, verification of scattering cross section generation in the thermal energy range is described.

Oral presentation

Development of nuclear data processing system FRENDY

Tada, Kenichi

no journal, , 

In JAEA, the nuclear data processing system FRENDY (FRom Evaluated Nuclear Data librarY to any application) has been developed. In this presentation, the overview and verification of FRENDY is described.

Oral presentation

Overview of nuclear data processing system FRENDY and current status of foreign countries

Tada, Kenichi; Nagaya, Yasunobu

no journal, , 

JAEA has developed the nuclear data processing code FRENDY (FRom Evaluated Nuclear Data librarY to any application) since 2013. In this presentation, we report the overview of the FRENDY code and current status of the nuclear data processing code development activity in the other countries.

Oral presentation

Development of nuclear data processing system FRENDY, 3; Construction of the probability table in the unresolved resonance region

Tada, Kenichi; Nagaya, Yasunobu

no journal, , 

JAEA has been developing the nuclear data processing code FRENDY (FRom Evaluated Nuclear Data librarY to any application). In this presentation, construction of the probability table in the unresolved resonance region is described.

Oral presentation

Present status of the FRENDY system development and future plans

Tada, Kenichi

no journal, , 

This presentation explains the overview of the nuclear data processing code FRENDY (FRom Evaluated Nuclear Data librarY to any application) under development in JAEA.

Oral presentation

Generation of an MVP library with a nuclear data processing system FRENDY

Nagaya, Yasunobu; Tada, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Development of nuclear data processing system FRENDY, 4; Implementation of the ACE file generator

Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi

no journal, , 

JAEA has been developing the nuclear data processing system FRENDY (FRom Evaluated Nuclear Data librarY to any application). The first goal of the development of FRENDY is generation function of the nuclear data library for the continuous energy Monte Carlo calculation code. To generate the nuclear data library, four procedures, i.e., (1) Generation of point wise cross section, (2) generation of the probability table, (3) processing the thermal scattering law data, and (4) generation of the nuclear data library, are required. In this presentation, generation of the ACE file which is the nuclear data library for the continuous energy Monte Carlo code is described. To verify FRENDY, the K$$_{rm eff}$$ values which is using the ACE file which is processed by FRENDY are compared with that by NJOY99. The difference of the K$$_{rm eff}$$ values are less than 0.05%. This result indicates that FRENDY appropriately generate the ACE file.

Oral presentation

Lecture 4; Processing of evaluated nuclear data file

Tada, Kenichi

no journal, , 

The nuclear data processing is very important process to connect the evaluated nuclear data file and nuclear transport calculation code. Because the nuclear data processing is carried out only when new or modified nuclear data file were released, it is difficult to cultivate the specialist of the nuclear data processing. To enhance understanding of the evaluated nuclear data file and nuclear data processing, this lecture explains the overview of them.

Oral presentation

Comparison of the processing results between FRENDY and NJOY

Tada, Kenichi

no journal, , 

JAEA has been developed the nuclear data processing system FRENDY from 2013. In this presentation, we explain the overview of FRENDY and comparison of the results processed by FRENDY and NJOY. To investigate the impact of the difference of the processing system on the neutronics calculation, we calculated the ICSBEP benchmark experiments, which are listed in INDC(NDS)-0701, and compared the k-eff values.

Oral presentation

Generation of thermal neutron scattering cross section from evaluated nuclear data

Tada, Kenichi

no journal, , 

The nuclear data processing is very important to generate cross section libraries for neutronics calculation codes. Though many researchers want to generate cross section libraries by themselves, only few researchers can generate them. This presentation explains the processing flow and method of the nuclear data processing from evaluated nuclear data file into the cross section library. This presentation also explains how to generate cross section library from experimental data or analytical results of thermal neutron scattering.

Oral presentation

Improvement of probability table generation using ladder method

Tada, Kenichi

no journal, , 

To improve the probability table generation, the more sophisticated method was introduced in the calculation methods of the Chi-Squared random numbers and the complex error function. We also investigated the impact of the ladder number on the probability table. We confirm that the calculation speed of new method is 20% faster than that of the old method.

Oral presentation

Implementation of random sampling for ACE-format cross sections using FRENDY

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

no journal, , 

The random sampling module for ACE format cross sections are developed using modules of FRENDY. This module perturbs the cross sections and other parameters in ACE format cross section library using covariance data. The GODIVA reactor is used and the calculation results of TSUNAMI-1D are compared to verify this module.

Oral presentation

Investigation of impact of ladder numbers on probability table

Tada, Kenichi

no journal, , 

The ladder number has large impact on the probability table generation time. In this paper, we investigate the appropriate ladder number to generate probability table. The calculation results indicate that the appropriate ladder number to generate probability table is 100.

21 (Records 1-20 displayed on this page)