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Journal Articles

Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region

Tada, Kenichi; Endo, Tomohiro*

Journal of Nuclear Science and Technology, 60(11), p.1397 - 1405, 2023/11

https://doi.org/10.1080/00223131.2023.2204102

Times Cited Count：1 Percentile：30.19(Nuclear Science & Technology)

The probability table method is a well-known method for addressing self-shielding effects in the unresolved resonance region. A long computational time is required to generate the probability table. The effective way to reduce the generation time of the probability table is the reduction of the number of ladders. The purpose of this study is the estimation of the optimal number of ladders using the statistical uncertainty in the probability table. To this end, the statistical uncertainty quantification method of the probability table was developed and the convergence behavior of the statistical uncertainty was investigated. The product of the probability table and the average cross section was considered the target of the statistical uncertainty. The convergence rate was affected by the average level spacing and reduced neutron width. The generation time of the probability table was less than half when the input parameter was changed from the number of ladders to the tolerance value.

JAEA Reports

Nuclear data processing code FRENDY version 2

Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Nagaya, Yasunobu

JAEA-Data/Code 2022-009, 208 Pages, 2023/02

JAEA-Data-Code-2022-009.pdf:3.87MB

The nuclear data processing code has an important role to connect evaluated nuclear data libraries and neutronics calculation codes. Japan Atomic Energy Agency (JAEA) has developed the nuclear data processing code FRENDY since 2013 to generate cross section files from evaluated nuclear data libraries, such as JENDL, ENDF/B, JEFF, and TENDL. The first version of FRENDY was released in 2019. FRENDY version 1 generates ACE files which are used for continuous energy Monte Carlo codes such as PHITS, Serpent, and MCNP. FRENDY version 2 generates multi-group neutron cross-section files from ACE files. The other major improvements are as follows: (1) uncertainty quantification for the probability tables of the unresolved resonance cross-section; (2) perturbation of the ACE file for the uncertainty quantification using a continuous Monte Carlo code; (3) modification of the ENDF-6 formatted nuclear data file. This report describes an overview of the nuclear data processing methods and input instructions for FRENDY.

Journal Articles

Nuclear data processing code FRENDY; A Verification with HTTR criticality benchmark experiments

Fujimoto, Nozomu*; Tada, Kenichi; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo

Annals of Nuclear Energy, 158, p.108270_1 - 108270_8, 2021/08

https://doi.org/10.1016/j.anucene.2021.108270

Times Cited Count：3 Percentile：33.11(Nuclear Science & Technology)

Journal Articles

Status of the neutron time-of-flight single-crystal diffraction data-processing software STARGazer

Yano, Naomine*; Yamada, Taro*; Hosoya, Takaaki*; Ohara, Takashi; Tanaka, Ichiro*; Niimura, Nobuo*; Kusaka, Katsuhiro*

Acta Crystallographica Section D; Structural Biology (Internet), 74(11), p.1041 - 1052, 2018/11

https://doi.org/10.1107/S2059798318012081

Times Cited Count：14 Percentile：72.51(Biochemical Research Methods)

Journal Articles

FRENDY; A New nuclear date processing system being developed at JAEA

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

EPJ Web of Conferences, 146, p.02028_1 - 02028_5, 2017/09

https://doi.org/10.1051/epjconf/201714602028

Times Cited Count：5 Percentile：91.74(Nuclear Science & Technology)

JAEA has started to develop new nuclear data processing system FRENDY (FRom Evaluated Nuclear Data libralY to any application). In this presentation, the outline of the development of FRENDY is presented. And functions and performances of FRENDY are demonstrated by generation and validation of the continuous energy cross section data libraries for MVP, PHITS and MCNP codes.

Journal Articles

Release of radioactive materials from high active liquid waste in small-scale hot test for boiling accident in reprocessing plant

Yamane, Yuichi; Amano, Yuki; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Yoshida, Kazuo; Ishikawa, Jun

Journal of Nuclear Science and Technology, 53(6), p.783 - 789, 2016/06

https://doi.org/10.1080/00223131.2015.1072065

Times Cited Count：7 Percentile：51.66(Nuclear Science & Technology)

The release behavior of radioactive materials from high active liquid waste (HALW) has been experimentally investigated under boiling accident conditions. In the experiments using HALW obtained through laboratory scale reprocessing, release ratio was measured for the FP nuclides such as Ru, $^{99}$ Tc, Cs, Sr, Nd, Y, Mo, Rh and actinides such as $^{242}$ Cm, $^{241}$ Am. As a result, the release ratio was 0.20 for Ru and 1 $10^{-4}$ for the FP and Ac nuclides. Ru was released into the gas phase in the form of both mist and gas. For its released amount, weak dependency was found to the initial concentration in the test solution. The release ratio decreased with the initial concentration. For other FP nuclides and actinides as non-volatile, released into the gas phase in the form of mist, the released amount increased with the initial concentration. The release ratio of Ru and NOx concentration increased with temperature of the test solutions. They were released almost at the same temperature between 200 and 300 $^{circ}$ C. Size distribution of the mist and other particle was measured.

JAEA Reports

Improvement on control system of the JT-60 radio frequency heating system

Shinozaki, Shinichi; Moriyama, Shinichi; Hiranai, Shinichi; Sato, Fumiaki*

JAERI-Tech 2003-032, 48 Pages, 2003/03

JAERI-Tech-2003-032.pdf:3.55MB

On the JT-60 radio frequency (RF) heating system, the decrease in the activity ratio was a problem because of the deterioration of the control system. To improve the reliability, we replaced CAMAC system for a power injection control system, which was a main cause of the trouble, with the microprocessor system. And, a function of computer supported programming function of RF power injection form was introduced, which contributed to reduce a load of operators. Furthermore, personal computers with network communication were introduced to improve a maintenance ability of the control system. As a result, the activity ratio of the RF heating system was improved significantly.

JAEA Reports

Visualization system on the earth simulator user's guide

Muramatsu, Kazuhiro; Sai, Kazunori*

JAERI-Data/Code 2002-017, 101 Pages, 2002/08

JAERI-Data-Code-2002-017.pdf:5.65MB

A visualization system on the Earth Simulator is developped. The system enables users to see a graphic representation of simulation results on a client terminal simultaneously with them being computed on the Earth Simulator. Moreover, the system makes it possible to change parameters of the calculation and its visualization in the middle of calculation. The graphical user interface of the system is constructed on a Java applet. Consequently, the client only needs a web browser, so it is independent of operating systems. The system consists of a server function, post-processing function and client function. This report describes mainly the usage of the server and post-processing functions.

JAEA Reports