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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

 Times Cited Count:1 Percentile:68.31(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.

Journal Articles

Statistical optimization of nZVI chemical synthesis approach towards P and NO$$_{3}$$$$^{-}$$ removal from aqueous solutions; Cost-effectiveness & parametric effects

Maamoun, I.; Eljamal, R.*; Eljamal, O.*

Chemosphere, 312, Part 1, p.137176_1 - 137176_11, 2023/01

 Times Cited Count:3 Percentile:40.21(Environmental Sciences)

JAEA Reports

Applicability of statistical geometry model to light water moderating systems

Mori, Takamasa; Kojima, Kensuke*; Suyama, Kenya

JAEA-Research 2018-010, 57 Pages, 2019/02

JAEA-Research-2018-010.pdf:6.25MB

In order to estimate applicability of the statistical geometry model (STGM) of MVP/GMVP, a parametric study in infinite geometry and criticality safety analyses for direct disposal of spent fuel in simple finite geometry have been carried out by using the MVP Monte Carlo code. It has been found that calculations with STGM for larger fuel spheres give larger thermal utilization factors and larger infinite multiplication factors compared with explicit random models in the range of fuel sphere packing fraction between 6.5 % and 63.3 %. Substantial differences are not observed between the results with two nearest neighbor distributions (NNDs); that given by the MCRDF code and the analytical expression based on a statistically uniform distribution. It is inferred that the overestimation by STGM is caused by the facts that STGM cannot take account of the surroundings of each neutron, whether a fuel sphere rich region or a water moderator rich one, because STGM always uses an NND averaged over such surroundings and that STGM, therefore, cannot take the effect of consecutive scatterings in the water moderator into account.

Journal Articles

Challenges for enhancing Fukushima environmental resilience, 10; Dose evaluation and risk communication

Saito, Kimiaki; Takahara, Shogo; Uezu, Yasuhiro

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(2), p.111 - 115, 2018/02

no abstracts in English

Journal Articles

Bayesian nonparametric analysis of crack growth rates in irradiated austenitic stainless steels in simulated BWR environments

Chimi, Yasuhiro; Takamizawa, Hisashi; Kasahara, Shigeki*; Iwata, Keiko; Nishiyama, Yutaka

Nuclear Engineering and Design, 307, p.411 - 417, 2016/10

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

To investigate influential parameters for irradiation-assisted stress corrosion cracking (IASCC) growth behavior, we attempt to analyze statistically existing data on the crack growth rate (CGR) in irradiated austenitic stainless steels (SSs) in boiling water reactor (BWR) environments using the Bayesian nonparametric (BNP) method. From the probability distribution of CGR and some input parameters, such as yield stress of irradiated material ($$sigma$$$$_{rm YS-irr}$$), stress intensity factor (${it K}$), electrochemical corrosion potential (ECP), and fast neutron fluence, the mean CGR is estimated and compared with the measured CGR. The analytical results show good reproducibility of the measured CGR. The results also indicate the possible neutron fluence effects on CGR in high CGR region (i.e., high neutron fluence condition) by radiation-induced segregation (RIS), localized deformation, and/or other mechanisms than radiation hardening.

Journal Articles

Development of an evaluation methodology for the natural circulation decay heat removal system in a sodium cooled fast reactor

Watanabe, Osamu*; Oyama, Kazuhiro*; Endo, Junji*; Doda, Norihiro; Ono, Ayako; Kamide, Hideki; Murakami, Takahiro*; Eguchi, Yuzuru*

Journal of Nuclear Science and Technology, 52(9), p.1102 - 1121, 2015/09

 Times Cited Count:13 Percentile:72.94(Nuclear Science & Technology)

A natural circulation (NC) evaluation methodology has been developed to ensure the safety of a sodium-cooled fast reactor (SFR) of 1500MW adopting the NC decay heat removal system (DHRS). The methodology consists of a 1D safety analysis which can evaluate the core hot spot temperature taking into account the temperature flattening effect in the core, a 3D fluid flow analysis which can evaluate the thermal-hydraulics for local convections and thermal stratifications in the primary system and DHRS, and a statistical safety evaluation method. The safety analysis method and the 3D analysis method have been validated using results of a 1/10 scaled water test simulating the primary system of the SFR and a 1/7 scaled sodium test simulating the primary system and the DHRS, and the applicability of the safety analysis for the SFR has been confirmed by comparing with the 3D analysis. Finally, a statistical safety evaluation has been performed for the SFR using the safety analysis method.

Journal Articles

Analytical study on biaxial strength of structural ceramics under tension-compression condition

Hanawa, Satoshi; Ishihara, Masahiro; Motohashi, Yoshinobu*

Key Engineering Materials, 297-300, p.40 - 46, 2005/11

no abstracts in English

Journal Articles

JENDL photonuclear data file

Kishida, Norio*; Murata, Toru*; Asami, Tetsuo*; Kosako, Kazuaki*; Maki, Koichi*; Harada, Hideo*; Lee, Y.*; Chang, J.*; Chiba, Satoshi; Fukahori, Tokio

AIP Conference Proceedings 769, p.199 - 202, 2005/05

Nuclear data for photonuclear reactions are required in the field of shielding design of high-energy electron accelerators and high-energy $$gamma$$-ray therapy. The JENDL Photonuclear Data File was prepared by a working group on nuclear data evaluations for photonuclear reactions in Japanese Nuclear Data Committee. From a survey of many literatures, it is difficult to construct the photonuclear data file by using only measured data, since there are not sufficient experimental data. We were therefore evaluating with theoretical calculations based on statistical nuclear reaction models. The photonuclear cross sections that are to be contained in the file are as follows: photoabsorption cross sections, yield cross sections and DDX for neutrons, protons, deuterons, tritons, $$^{3}$$He-particles and alpha-particles, and isotope production cross sections. For the actinide nuclides, photofission cross sections are also included. The maximum energy of incident photons is 140 MeV and stored are the photonuclear data for 68 nuclides from $$^{2}$$H to $$^{237}$$Np.

Journal Articles

Study on brittle fracture model for multiaxial tensile stress

Hanawa, Satoshi; Ishihara, Masahiro; Motohashi, Yoshinobu*

Zairyo, 54(2), p.201 - 206, 2005/02

no abstracts in English

Journal Articles

Searching for pattern-forming asynchronous cellular automata; An Evolutionary approach

Suzudo, Tomoaki

Lecture Notes in Computer Science 3305, p.151 - 160, 2004/00

This paper discuss a class of 2-dimensional asynchronous cellular automata with conservation of mass, for the formation of patterns in groups. The previous study reported a methodology of searching, automatically, for pattern-forming cellular automata using a genetic algorithm; this approach successfully found a few types of pattern-forming rules. The current study is a series of statistical analyses of one of the classes found by the above methodology, with the hope of understanding the mechanisms of the pattern formation. These analyses lead to some basic logic necessary to the pattern formation, but not to enough information to elucidate the whole mechanism of the pattern formation. This result suggests that the existence of unidentified cooperative operations between the different transitions of the cellular automaton rule to carry out the pattern formation.

JAEA Reports

Nuclear data evaluation for $$^{237}$$Np, $$^{241}$$Am, $$^{242g}$$Am and $$^{242m}$$Am irradiated by neutrons and protons at energies up to 250 MeV

Konobeyev, A. Y.; Fukahori, Tokio; Iwamoto, Osamu

JAERI-Research 2002-032, 36 Pages, 2002/12

JAERI-Research-2002-032.pdf:1.33MB

The evaluation of nuclear data has been performed for $$^{237}$$Np, $$^{241}$$Am, $$^{242g}$$Am and $$^{242m}$$. Neutron data were obtained at the energies from 20 to 250 MeV and combined with JENDL-3.3 data at 20 MeV. Evaluation of the proton data has been done from 1 to 250 MeV. The coupled channel optical model was used to obtain angular distributions for elastic and inelastic scattering and transmission coefficients. Pre-equilibrium exciton model and Hauser-Feshbach statistical model were used to describe neutron and charged particles emission from the excited nuclei. These evaluation is the first work for producing the full set of evaluated file up to 250 MeV for $$^{237}$$Np and americium isotopes.

JAEA Reports

Nuclear data evaluation for $$^{238}$$Pu, $$^{239}$$Pu, $$^{240}$$Pu, $$^{241}$$Pu and $$^{242}$$Pu irradiated by neutrons and protons at the energies up to 250 MeV

Konobeyev, A. Y.; Fukahori, Tokio; Iwamoto, Osamu

JAERI-Research 2002-029, 48 Pages, 2002/12

JAERI-Research-2002-029.pdf:1.53MB

The evaluation of nuclear data for plutonium isotopes with atomic mass number from 238 to 242 has been performed. Neutron data were obtained at the energies from 20 to 250 MeV and combined with JENDL-3.3 data at 20 MeV. Evaluation of the proton data has been done from 1 to 250 MeV. The coupled channel optical model was used to obtain angular distributions for elastic and inelastic scattering and transmission coefficients. Pre-equilibrium exciton model and Hauser-Feshbach statistical model were used to describe neutron and charged particles emission from the excited nuclei. These evaluation is the first work for producing the full set of evaluated file up to 250 MeV for plutonium isotopes.

Journal Articles

The MCNP5 random number generator

Brown, B.*; Nagaya, Yasunobu

Transactions of the American Nuclear Society, 87, p.230 - 232, 2002/11

no abstracts in English

JAEA Reports

Evaluation of neutron-induced reactions on $$^{236}$$Pu for JENDL-3.3

Iwamoto, Osamu; Nakagawa, Tsuneo

JAERI-Research 2002-013, 18 Pages, 2002/07

JAERI-Research-2002-013.pdf:0.7MB

Cross sections and energy-angular distributions of emitted neutrons were evaluated for the neutron-incident reactions on $$^{236}$$Pu in the incident energy range of 10eV to 20MeV by using a statistical model combined with a coupled channel optical model. The calculated results were compiled to the latest evaluated nuclear data library JENDL-3.3 in the ENDF-6 format. The unresolved resonance region is assumed to be from 10eV to 30keV, and the averaged resonance parameters were obtained to reproduce the calculated cross sections. Maxwell temperatures for fission neutron spectra were estimated from a systematics with a correction for prefission neutrons.

Journal Articles

Proposal of a brittle fracture model based on pore and crack interaction effect

Ishihara, Masahiro; Takahashi, Tsuneo*

Zairyo, 51(4), p.425 - 430, 2002/04

no abstracts in English

Journal Articles

Monte Carlo analysis of HTTR with the MVP statistical geometry model

Mori, Takamasa; Okumura, Keisuke; Nagaya, Yasunobu; Ando, Hiroei

Transactions of the American Nuclear Society, 83, p.283 - 284, 2000/00

no abstracts in English

Journal Articles

Evaluation of neutron- and proton-induced nuclear data on $$^{27}$$Al up to 2GeV

Y.-O.Lee*; J.Chang*; Fukahori, Tokio; Chiba, Satoshi

Journal of Nuclear Science and Technology, 36(12), p.1125 - 1134, 1999/12

 Times Cited Count:10 Percentile:60.71(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Statistics and predictions of population, energy and environment problems

Sobajima, Makoto

JAERI-Review 99-004, 64 Pages, 1999/03

JAERI-Review-99-004.pdf:3.05MB

no abstracts in English

Journal Articles

Study for a novel tomography technique using an imaging plate

*; *; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 424(1), p.221 - 228, 1999/00

 Times Cited Count:4 Percentile:38.4(Instruments & Instrumentation)

no abstracts in English

79 (Records 1-20 displayed on this page)