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Journal Articles

Self-shielding effect of unresolved resonance data in JENDL-4.0

Konno, Chikara; Kato, Yoshinari*; Takakura, Kosuke; Ota, Masayuki; Ochiai, Kentaro; Sato, Satoshi

Progress in Nuclear Science and Technology (Internet), 4, p.606 - 609, 2014/04

At International Conference on Nuclear Data for Science and Technology in 2007 we pointed out that most of unresolved resonance data in JENDL-3.3 have a problem related to self-shielding correction. Here with a simple calculation model we investigated if the newest JENDL, JENDL-4.0, was improved for the problem or not. As a result, it seems that unresolved resonance data in JENDL-4.0 have no problem, but we are afraid that the self-shielding effect for the unresolved resonance data in JENDL-4.0 is too large. New integral experiments for unresolved resonance data are strongly recommended in order to verify unresolved resonance data.

Journal Articles

Benchmark test of JENDL-4.0 with TOF experiments at Osaka Univ./OKTAVIAN

Kato, Yoshinari*; Takakura, Kosuke; Ota, Masayuki; Ochiai, Kentaro; Sato, Satoshi; Konno, Chikara

Progress in Nuclear Science and Technology (Internet), 4, p.596 - 600, 2014/04

We have performed benchmark tests for JENDL-4.0 released last year in shielding and fusion neutronics fields. Now we analyze OKTAVIAN TOF experiments (CF$$_{2}$$, Si, Ti, Cr, Mn, Co, Cu, As, Se, Zr, Nb, Mo, W) with JENDL-4.0 in order to validate JENDL-4.0. For comparison we also do with the older version JENDL-3.3 and other recent nuclear data libraries (ENDF/B-VII.0, JEFF-3.11). The Monte Carlo code MCNP-4C was used for these analyses. We adopted the official ACE files for JENDL-4.0, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0. As a result, the following results are obtained through comparison between calculation and measured results. (1) Si, As, Se, Mo, W : Calculation results with JENDL-4.0 agree with the measured ones better than those with JENDL-3.3. (2) CF$$_{2}$$, Co, Cu, Ti, Zr : Calculation results with JENDL-4.0 are almost the same as those with JENDL-3.3. (3) Cr, Mn, Nb : Calculation results with JENDL-4.0 are partially better and partially worse than those with JENDL-3.3.

Oral presentation

Validation of multigroup library MATXSLIB-J40 based on JENDL-4.0

Konno, Chikara; Kato, Yoshinari; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi

no journal, , 

JENDL-4, the major revised version of Japanese Evaluated Nuclear Data Library (JENDL), was released in May, 2010. Its official multigroup library MATXSLIB-4.0 of 199 neutron groups and 42 $$gamma$$ groups with up-scattering data and thermal scattering law data was also released in September, 2010. In this study we examined a validation of MATXSLIB-J40 through analyses of benchmark experiments at JAEA/FNS with Sn codes and the Monte Carlo code MCNP. As a result, the following results are obtained. (1) The calculated results with Sn codes and MATXSLIB-J40 agree well with the measured data and the calculated ones with MCNP. The self-shielding correction in MATXSLIB-J40 has no problem. (2) It is notable that thermal neutron peaks, which were hard to represent, are adequately calculated. It is strongly recommended that a multigroup library of the next Fusion Evaluated Nuclear Data Library (FENDL), FENDL-3, should also have 199 neutron groups, up-scattering data and thermal scattering law data.

Oral presentation

Benchmark test of MATXSLIB-J40 produced from JENDL-4.0

Konno, Chikara; Kato, Yoshinari; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi

no journal, , 

JENDL-4, the major revised version of Japanese Evaluated Nuclear Data Library (JENDL), was released in May, 2010. Its official multigroup library MATXSLIB-4.0 of 199 neutron groups and 42 $$gamma$$ groups with up-scattering data and thermal scattering law data was also released in September, 2010. In this study we examined a validation of MATXSLIB-J40 through analyses of benchmark experiments at JAEA/FNS with Sn codes and the Monte Carlo code MCNP. As a result, the following results are obtained. (1) The calculated results with Sn codes and MATXSLIB-J40 agree well with the measured data and the calculated ones with MCNP. The self-shielding correction in MATXSLIB-J40 has no problem. (2) It is notable that thermal neutron peaks, which were hard to represent, are adequately calculated. It is strongly recommended that a multigroup library of the next Fusion Evaluated Nuclear Data Library (FENDL), FENDL-3, should also have 199 neutron groups, up-scattering data and thermal scattering law data.

Oral presentation

Benchmark test of JENDL-4.0 with TOF experiments at Osaka Univ./OKTAVIAN

Kato, Yoshinari; Ochiai, Kentaro; Takakura, Kosuke; Sato, Satoshi; Konno, Chikara

no journal, , 

We have performed benchmark tests for JENDL-4.0 released last year in shielding and fusion neutronics fields. Now we analyze OKTAVIAN TOF experiments (CF$$_{2}$$, Si, Ti, Cr, Mn, Co, Cu, As, Se, Zr, Nb, Mo, W) with JENDL-4.0 in order to validate JENDL-4.0. For comparison we also do with the older version JENDL-3.3 and other recent nuclear data libraries (ENDF/B-VII.0, JEFF-3.11). The Monte Carlo code MCNP-4C was used for these analyses. We adopted the official ACE files for JENDL-4.0, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0. As a result, the following results are obtained through comparison between calculation and measured results. (1) As, Se, W: Calculation results with JENDL-4.0 agree with the measured ones better than those with JENDL-3.3. (2) CF$$_{2}$$, Si, Co, Mn, Cu, Ti, Mo, Zr: Calculation results with JENDL-4.0 are almost the same as those with JENDL-3.3. (3) Cr, Nb: Calculation results with JENDL-4.0 are partially better and partially worse than those with JENDL-3.3.

Oral presentation

Benchmark test of JENDL-4.0 with TOF experiments at Osaka Univ./OKTAVIAN, 2

Kato, Yoshinari; Ochiai, Kentaro; Takakura, Kosuke; Sato, Satoshi; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

Self-shielding effects of unresolved resonance data in JENDL-4.0

Konno, Chikara; Kato, Yoshinari; Takakura, Kosuke; Ota, Masayuki; Ochiai, Kentaro; Sato, Satoshi

no journal, , 

At International Conference on Nuclear Data for Science and Technology in 2007 we pointed out that most of unresolved resonance data in JENDL-3.3 have a problem related to self-shielding correction. Here with a simple calculation model we investigated if the newest JENDL, JENDL-4.0, was improved for the problem or not. As a result, it seems that unresolved resonance data in JENDL-4.0 have no problem, but we are afraid that the self-shielding effect for the unresolved resonance data in JENDL-4.0 is too large. New integral experiments for unresolved resonance data are strongly recommended in order to verify unresolved resonance data.

Oral presentation

Investigation of an appropriate scanning speed for finding contamination at radiation workplace

Kato, Yoshinari; Usui, Toshihide; Gomibuchi, Masaru

no journal, , 

no abstracts in English

Oral presentation

Investigation of radiation contamination of workers' masks for contamination at Plutonium Fuel Research Facility of Oarai Research and Development Center

Kato, Yoshinari; Hashimoto, Makoto; Miyauchi, Hideaki; Yasumune, Takashi; Ogawa, Ryuichiro; Goto, Shingo; Ochiai, Yukihiro*; Matsui, Junki

no journal, , 

no abstracts in English

Oral presentation

Contamination at Plutonium Fuel Research Facility of Oarai Research and Development Center, 3; Measurement and data aggregation of radiation contamination for workers' dose evaluation

Kato, Yoshinari; Hashimoto, Makoto; Miyauchi, Hideaki; Yasumune, Takashi; Maeda, Eita; Takasaki, Koji; Yoshizawa, Michio; Momose, Takumaro

no journal, , 

no abstracts in English

Oral presentation

Contamination at Plutonium Fuel Research Facility of Oarai Research and Development Center; Evaluation of the activity median aerodynamic diameter of plutonium and americium particles by using imaging plates

Yasumune, Takashi; Kato, Yoshinari; Maeda, Eita; Miyauchi, Hideaki; Hashimoto, Makoto; Takasaki, Koji

no journal, , 

no abstracts in English

11 (Records 1-11 displayed on this page)
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