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Journal Articles

ACE library of JENDL-4.0/HE

Matsuda, Norihiro; Kunieda, Satoshi; Okamoto, Tsutomu*; Tada, Kenichi; Konno, Chikara

Progress in Nuclear Science and Technology (Internet), 6, p.225 - 229, 2019/01

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

Burn-up characteristics and criticality effect of impurities in the graphite structure of a commercial-scale prismatic HTGR

Fukaya, Yuji; Goto, Minoru; Nishihara, Tetsuo

Nuclear Engineering and Design, 326, p.108 - 113, 2018/01

 Percentile:100(Nuclear Science & Technology)

Burn-up characteristics and criticality of impurity contained into graphite structure for commercial scale prismatic High Temperature Gas-cooled Reactor (HTGR) have been investigated. For HTGR, of which the core is filled graphite structure, the impurity contained into the graphite has unignorable poison effect for criticality. Then, GTHTR300, commercial scale HTGR, employed high grade graphite material named IG-110 to take into account the criticality effect for the reflector blocks next to fuel blocks. The fuel blocks, which should also employ IG-110, employ lower grade graphite material named IG-11 from the economic perspective. In this study, the necessity of high grade graphite material for commercial scale HTGR is reconsidered by evaluating the burn-up characteristics and criticality of the impurity. The poison effect of the impurity, which is used to be expressed by a boron equivalent, reduces exponentially like burn-up of $$^{10}$$B, and saturate at a level of 1 % of the initial value of boron equivalent. On the other hand, the criticality effect of the boron equivalent of 0.03 ppm, which corresponds to a level of 1 % of IG-11 shows ignorable values lower than 0.01 %$$Delta$$k/kk' for both of fuel blocks and reflector blocks. The impurity can be represented by natural boron without problem. Therefore, the poison effect of the impurity is evaluated with whole core burn-up calculations. As a result, it is concluded that the impurity is not problematic from the viewpoint of criticality for commercial scale HTGR because it is burned clearly until End of Cycle (EOC) even with the low grade graphite material of IG-11. According to this result, more economic electricity generation with HTGR is expected by abolishing the utilization of IG-110.

Journal Articles

New remarks on KERMA factors and DPA cross section data in ACE files

Konno, Chikara; Sato, Satoshi; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro

Fusion Engineering and Design, 109-111(Part.B), p.1649 - 1652, 2016/11

Recently we have examined KERMA factors and DPA cross section data in the latest official ACE files of JENDL-4.0, ENDF/B-VII.1, JEFF-3.2 and FENDL-3.0 in more detail and we found out the following new problems on the KERMA factors and DPA cross section data. (1) NJOY bugs and incorrect nuclear data generated KERMA factors and DPA cross section data of no increase with decreasing neutron energy in low neutron energy. (2) Huge helium production data caused drastically large KERMA factors and DPA cross section data in low neutron energy. (3) It seemed that NJOY could not adequately process capture cross section data in File 6, not File 12-15. (4) KERMA factors with the kinematics method are not correct for nuclear data libraries without detailed secondary particle data (energy-angular distribution data). These problems should be resolved based on our study.

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.

Journal Articles

DPA Calculation in Japanese Spallation Neutron Source

Harada, Masahide; Watanabe, Noboru; Konno, Chikara; Meigo, Shinichiro; Ikeda, Yujiro; Niita, Koji*

Journal of Nuclear Materials, 343(1-3), p.197 - 204, 2005/06

 Times Cited Count:21 Percentile:14.34(Materials Science, Multidisciplinary)

For a construction of maintenance and storage scenarios for JSNS, lives of structure material need to be estimated. DPA (Displacement per Atom) was a major index of radiation damage. So we evaluated DPA value of each component. Function of the DPA calculation was equipped to the PHITS code, which was particle and heavy ion transport code. For DPA calculation, displacement cross section was necessary. Displacement cross sections of neutron below 150 MeV were processed by the NJOY code from LA150 library and those of neutron above 150MeV and proton in the all energy region were obtained from energies of fragments calculated in the PHITS. By using the PHITS, we calculated DPA values and DPA mapping. We obtained that the peak DPA values at end of 5000MWh operation were 4.1 for target vessel, 2.8 for reflector and moderator vessels, and 0.4 for proton beam windows, respectively. We estimated the target life at 1 year and the moderator life at 6 year.

JAEA Reports

The Libraries FSXLIB and MATXSLIB based on JENDL-3.3

Kosako, Kazuaki*; Yamano, Naoki*; Fukahori, Tokio; Shibata, Keiichi; Hasegawa, Akira

JAERI-Data/Code 2003-011, 38 Pages, 2003/07

JAERI-Data-Code-2003-011.pdf:1.29MB

The third revision of JENDL-3 (JENDL-3.3) was released in May 2002. The library is useful for many applications. For users' convenience, we have produced two JENDL-3.3 based libraries FSXLIB-J33 and MATXSLIB-J33 for transport calculation codes such as MCNP and ANISN. These two libraries are available on request.

Journal Articles

MATXS files processed from JENDL-3.2 and -3.3 for shielding

Konno, Chikara; Ikeda, Yujiro

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1037 - 1040, 2002/08

no abstracts in English

Journal Articles

DORT analyses of decay heat experiment on tungsten for ITER

Konno, Chikara; Maekawa, Fujio; Wada, Masayuki*; Ikeda, Yujiro; Takeuchi, Hiroshi

Fusion Engineering and Design, 58-59, p.961 - 965, 2001/11

 Percentile:100

no abstracts in English

JAEA Reports

Development of automatic editing system for MCNP library "autonj"

Maekawa, Fujio; Sakurai, Kiyoshi; Kosako, Kazuaki*; Kume, Etsuo; Kawasaki, Nobuo*; Nomura, Yasushi; Naito, Yoshitaka*

JAERI-Data/Code 99-048, p.52 - 0, 1999/12

JAERI-Data-Code-99-048.pdf:2.34MB

no abstracts in English

JAEA Reports

Integral test of JENDL Dosimetry File 99 with high flux neutron field

Shimakawa, Satoshi

JAERI-Data/Code 99-043, p.75 - 0, 1999/09

JAERI-Data-Code-99-043.pdf:3.38MB

no abstracts in English

JAEA Reports

Vectorization, parallelization and porting of nuclear codes on the VPP500 system, porting; Progress report fiscal 1996

*; *; *; *; *; *; ; ; Kume, Etsuo;

JAERI-Data/Code 97-055, 161 Pages, 1998/01

JAERI-Data-Code-97-055.pdf:4.57MB

no abstracts in English

Journal Articles

Production and verification of the MCNP cross section library FSXLIB-J3R2 based on JENDL-3.2

Kosako, Kazuaki*; Yamano, Naoki*; Maekawa, Fujio; Oyama, Yukio

Proc., 1996 Topical Meeting on Radiation Protection and Shielding, 1, p.1088 - 1095, 1996/00

no abstracts in English

JAEA Reports

FSXLIB-J3R2: A continuous energy cross section library for MCNP based on JENDL-3.2

Kosako, Kazuaki*; Maekawa, Fujio; Oyama, Yukio; Uno, Yoshitomo; Maekawa, Hiroshi

JAERI-Data/Code 94-020, 42 Pages, 1994/12

JAERI-Data-Code-94-020.pdf:1.18MB

no abstracts in English

JAEA Reports

Shielding benchmark tests of JENDL-3

Kawai, Masayoshi*; ; *; Yamano, Naoki*; *; *; *; *; Sakurai, Kiyoshi

JAERI 1330, 129 Pages, 1994/03

JAERI-1330.pdf:5.52MB

no abstracts in English

JAEA Reports

Effects of neutron data libraries and criticality codes on IAEA criticality benchmark problems

M.M.Sarker*; ; Masukawa, Fumihiro; Naito, Yoshitaka

JAERI-M 93-203, 39 Pages, 1993/10

JAERI-M-93-203.pdf:1.0MB

no abstracts in English

Journal Articles

FSXLIB-J3: MCNP continuous cross section library based on JENDL-3

Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Hiroshi

Proc. of the Topical Meeting on New Horizons in Radiation Protection and Shielding, p.357 - 363, 1992/00

no abstracts in English

31 (Records 1-20 displayed on this page)