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Journal Articles

CIELO collaboration summary results; International evaluations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.

Nuclear Data Sheets, 148, p.189 - 213, 2018/02

 Times Cited Count:8 Percentile:4(Physics, Nuclear)

The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - $$^{235}$$U, $$^{238}$$U, $$^{239}$$Pu, $$^{56}$$Fe, $$^{16}$$O and $$^{1}$$H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.

Journal Articles

The CCONE code system and its application to nuclear data evaluation for fission and other reactions

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Shibata, Keiichi

Nuclear Data Sheets, 131, p.259 - 288, 2016/01

 Times Cited Count:21 Percentile:5.23(Physics, Nuclear)

A computer code system, CCONE, was developed for nuclear data evaluation in the JENDL project. The CCONE code system integrates various nuclear reaction models needed to describe nucleon, light charged nuclei up to alpha-particle and photon induced reactions. The code is written in the C++ programming language using an object-oriented technology. At first, it was applied to neutron-induced reaction data on actinides, which were compiled into JENDL Actinide File 2008 and JENDL-4.0. It has been extensively used in various nuclear data evaluation not only for actinides but also for non-actinide nuclei. The CCONE code has been upgraded to nuclear data evaluation at higher incident energies for neutron-, proton-, and photon-induced reactions. It was also used for estimating $$beta$$-delayed neutron emission. This paper describes the CCONE code system indicating the concept and design of coding and inputs. Details of formulation formodelings of the direct, pre-equilibrium and compound reactions are presented. Applications to the nuclear data evaluations such as neutron-induced reactions on actinides and medium-heavy nuclei, high-energy nucleon-induced reactions, photonuclear reaction and $$beta$$-delayed neutron emission are mentioned.

Journal Articles

Covariance of neutron cross sections for $$^{16}$$O through R-matrix analysis

Kunieda, Satoshi; Kawano, Toshihiko*; Paris, M.*; Hale, G. M.*; Shibata, Keiichi; Fukahori, Tokio

Nuclear Data Sheets, 123, p.159 - 164, 2015/01

 Times Cited Count:3 Percentile:61.22(Physics, Nuclear)

The collision matrix in the R-matrix theory is unitary, hence theory brings strong constraints to behavior of the parameters. An unitarity-imposed R-matrix analysis is carried out for $$^{17}$$O system to evaluate $$^{16}$$O neutron cross-sections in the resolved resonance range. Covariance matrices are also estimated both for the cross-sections and angular distributions with a deterministic method. Present results mirror the nature in the theory as well as experimental information.

Journal Articles

Use and impact of covariance data in a Japanese latest adjusted library ADJ2010 based on JENDL-4.0

Yokoyama, Kenji; Ishikawa, Makoto

Nuclear Data Sheets, 123, p.97 - 103, 2015/01

 Times Cited Count:4 Percentile:52.29(Physics, Nuclear)

The current status of covariance applications to fast reactor analysis and design in Japan is summarized. To improve the accuracy of core design values by adopting the integral data such as the critical experiments and the power reactor operation data, the cross-section adjustment based on the Bayesian theorem is used. After the release of JENDL-4.0, a development project of the new adjusted group-constant set ADJ2010 was started and completed in 2013. In the present paper, the final results of ADJ2010 are briefly described. In addition, the adjustment results of ADJ2010 are discussed from the viewpoint of use and impact of nuclear data covariances. For this purpose, three kind of indices, called "degree of mobility", "adjustment motive force", and "adjustment potential", are newly proposed.

Journal Articles

New approach for nuclear reaction model in the combination of intra-nuclear cascade and DWBA

Hashimoto, Shintaro; Iwamoto, Osamu; Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*

Nuclear Data Sheets, 118, p.258 - 261, 2014/05

 Times Cited Count:4 Percentile:55.88(Physics, Nuclear)

Particle transport simulation codes based on the Monte Carlo technique are utilized to predict interaction of radiations with materials. The codes describe the transport of all particles, e.g. photons, electrons, nucleons, and heavy ions by various models for physical processes and nuclear reaction. In particular, nuclear reaction processes are essential parts for the accurate prediction. Recently, accelerator-based neutron sources using proton or deuteron beams with energies from 10 to 100 MeV come to be utilized for scientific and medical applications. For neutron source design, accurate description of neutron yields created by nuclear reactions is required in the simulation. However, the Intra-Nuclear Cascade type models used in most of the simulation codes are not enough to reproduce experimental data because of neglecting quantum mechanical effects. In this study, we combined the cascade type models and an event generator using the DWBA (Distorted Wave Born Approximation) calculation, which is a theoretical model based on quantum mechanics. We verified that the calculated results with the combination model can reproduce experimental data of neutron spectra in deuteron-induced reactions. We will also present the validity of the combination model for proton-induced reactions.

Journal Articles

Measurement of 100- and 290-MeV/A carbon incident neutron production cross sections for carbon, nitrogen and oxygen

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Takamiya, Masanori*; Hashiguchi, Taro*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; et al.

Nuclear Data Sheets, 119, p.303 - 306, 2014/05

 Percentile:100(Physics, Nuclear)

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and $$gamma$$-ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of the secondary neutrons yields data is essential for assessment of radiation safety on both of workers and public in treatment facilities. We have measured the neutron yields from carbon ion incidence on carbon, nitrogen and oxygen targets in wide angular range from 15$$^{circ}$$ to 90$$^{circ}$$ with 100- and 290-MeV/u.

Journal Articles

Measurements of neutron capture cross sections of $$^{112}$$Sn and $$^{118}$$Sn with J-PARC/MLF/ANNRI

Kimura, Atsushi; Hirose, Kentaro; Nakamura, Shoji; Harada, Hideo; Hara, Kaoru; Hori, Junichi*; Igashira, Masayuki*; Kamiyama, Takashi*; Katabuchi, Tatsuya*; Kino, Koichi*; et al.

Nuclear Data Sheets, 119, p.150 - 153, 2014/05

 Times Cited Count:3 Percentile:63.98(Physics, Nuclear)

Journal Articles

Cross section measurements of the radioactive $$^{107}$$Pd and stable $$^{105,108}$$Pd nuclei at J-PARC/MLF/ANNRI

Nakamura, Shoji; Kimura, Atsushi; Kitatani, Fumito; Ota, Masayuki; Furutaka, Kazuyoshi; Goko, Shinji*; Hara, Kaoru; Harada, Hideo; Hirose, Kentaro; Kin, Tadahiro*; et al.

Nuclear Data Sheets, 119, p.143 - 146, 2014/05

 Times Cited Count:4 Percentile:55.88(Physics, Nuclear)

We have started the measurements of the neutron-capture cross sections for stable $$^{105,108}$$Pd nuclei as well as the radioactive $$^{107}$$Pd. The neutron-capture cross-section measurements by the time-of flight method were performed using an apparatus called "Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI)" installed at the neutron Beam Line No.4 of the Materials and Life science experimental Facility (MLF) in the J-PARC. The neutron-capture cross sections of $$^{107}$$Pd and $$^{105,108}$$Pd have been measured in the neutron energy range from thermal to 300 eV. Some new information was obtained for resonances of these Pd nuclei.

Journal Articles

Surrogate reactions research at JAEA/Tokyo Tech

Chiba, Satoshi; Nishio, Katsuhisa; Makii, Hiroyuki; Aritomo, Yoshihiro*; Nishinaka, Ichiro; Ishii, Tetsuro; Tsukada, Kazuaki; Asai, Masato; Furutaka, Kazuyoshi; Hashimoto, Shintaro; et al.

Nuclear Data Sheets, 119, p.229 - 232, 2014/05

 Percentile:100(Physics, Nuclear)

Journal Articles

Capture cross-section measurement of $$^{241}$$Am(n,$$gamma$$) at J-PARC/MLF/ANNRI

Harada, Hideo; Ota, Masayuki; Kimura, Atsushi; Furutaka, Kazuyoshi; Hirose, Kentaro; Hara, Kaoru; Kin, Tadahiro*; Kitatani, Fumito; Koizumi, Mitsuo; Nakamura, Shoji; et al.

Nuclear Data Sheets, 119, p.61 - 64, 2014/05

 Times Cited Count:17 Percentile:14.77(Physics, Nuclear)

Journal Articles

Measurements of capture $$gamma$$ rays from the neutron resonances of $$^{74}$$Se and $$^{77}$$Se at the J-PARC/MLF/ANNRI

Hori, Junichi*; Yashima, Hiroshi*; Nakamura, Shoji; Furutaka, Kazuyoshi; Hara, Kaoru; Harada, Hideo; Hirose, Kentaro; Kimura, Atsushi; Kitatani, Fumito; Koizumi, Mitsuo; et al.

Nuclear Data Sheets, 119, p.128 - 131, 2014/05

 Times Cited Count:3 Percentile:63.98(Physics, Nuclear)

In this work, we measured the capture $$gamma$$ rays from the neutron resonances of $$^{74}$$Se and $$^{77}$$Se. A neutron time-of-flight method was adopted for the measurements with a 4$$pi$$ Ge spectrometer installed at the Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) in the J-PARC Material and Life science experimental Facility (MLF). The $$gamma$$-ray pulse-height spectra corresponding to the 27-eV resonance of $$^{74}$$Se and the 113-, 212-, 291-, 342-, 690- and 864-eV resonances of $$^{77}$$Se were obtained by gating on the TOF regions, respectively. The relative intensities of those primary transitions were derived and compared with the previous experimental data. For the 27-eV resonance of $$^{74}$$Se, a strong primary transition to the 293-keV state was observed. As for $$^{77}$$Se, the quite differences of the decay pattern were found between the resonances.

Journal Articles

Cross section measurement of $$^{237}$$Np$$(n,gamma)$$ at J-PARC/MLF/ANNRI

Hirose, Kentaro; Furutaka, Kazuyoshi; Hara, Kaoru; Harada, Hideo; Hori, Junichi*; Igashira, Masayuki*; Kamiyama, Takashi*; Katabuchi, Tatsuya*; Kimura, Atsushi; Kin, Tadahiro*; et al.

Nuclear Data Sheets, 119, p.48 - 51, 2014/05

 Times Cited Count:1 Percentile:85.28(Physics, Nuclear)

Journal Articles

Development of anti-Compton LaBr$$_{3}$$(Ce) spectrometer for measurement of surrogate reactions

Makii, Hiroyuki; Ota, Shuya*; Ishii, Tetsuro; Nishio, Katsuhisa; Nishinaka, Ichiro; Furutaka, Kazuyoshi; Wakabayashi, Yasuo*; Chiba, Satoshi*; Igashira, Masayuki*

Nuclear Data Sheets, 119, p.361 - 364, 2014/05

 Percentile:100(Physics, Nuclear)

Anti-Compton LaBr$$_{3}$$(Ce) spectrometers have been installed at JAEA-Tokai tandem accelerator facility in order to measure the $$gamma$$ rays from the highly excited states produced by surrogate reactions. Each spectrometer consists of a central LaBr$$_{3}$$(Ce) detector with a diameter of 10.2 cm and a length of 12.7 cm, and an annular BGO detector with a thickness of 2.5 cm and a length of 25.4 cm. In this contribution, we will present the results of performance test using the standard $$gamma$$ ray source and high-energy $$gamma$$ rays from the $$^{27}$$Al(p,$$gamma$$)$$^{28}$$Si reaction, and a measurement plan for (n,$$gamma$$) cross sections using a surrogate reaction at JAEA-Tokai tandem accelerator facility.

Journal Articles

Partial photoneutron cross sections for $$^{207,208}$$Pb

Kondo, Takeo*; Utsunomiya, Hiroaki*; Goriely, S.*; Iwamoto, Chihiro*; Akimune, Hidetoshi*; Yamagata, Tamio*; Toyokawa, Hiroyuki*; Harada, Hideo; Kitatani, Fumito; Lui, Y.-W.*; et al.

Nuclear Data Sheets, 119, p.310 - 313, 2014/05

 Times Cited Count:1 Percentile:85.28(Physics, Nuclear)

Journal Articles

Analysis of Pu isotopes in melted fuel by neutron resonance transmission; Examination by linear absorption model

Kitatani, Fumito; Harada, Hideo; Takamine, Jun; Kureta, Masatoshi; Seya, Michio

Nuclear Data Sheets, 118, p.505 - 509, 2014/04

 Times Cited Count:1 Percentile:85.28(Physics, Nuclear)

Feasibility study of neutron resonance transmission analysis (NRTA) has been started to quantify nuclear materials in particle-like debris of melted fuel formed in severe accidents of nuclear reactor such as Fukushima Daiichi Nuclear Power Plants. The achievable measurement accuracy was examined by NRTA using a linear absorption model for the sample in which substances other than nuclear fuel materials, such as boron, were contained. In this study, boron and iron were considered to be contained in spent nuclear fuel as impurities. The neutron flight path is 5 m, that is the length between the neutron source and a neutron detector. Neutron absorption spectra were calculated using the total neutron absorption cross-section by JENDL-4.0. The absorption spectra together with their errors were evaluated. The achievable accuracy of Pu isotopic density was deduced as a function of neutron intensity and impurity density. This research was supported by JSGO/MEXT.

Journal Articles

Neutron resonance densitometry for particle-like debris of melted fuel

Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Takamine, Jun; Kureta, Masatoshi; Tsuchiya, Harufumi; Iimura, Hideki; Seya, Michio; Becker, B.*; Kopecky, S.*; et al.

Nuclear Data Sheets, 118, p.502 - 504, 2014/04

 Times Cited Count:3 Percentile:63.98(Physics, Nuclear)

Journal Articles

R-matrix analysis for n + $$^{16}$$O cross-sections up to E$$_{rm n}$$ = 6.0 MeV with covariances

Kunieda, Satoshi; Kawano, Toshihiko*; Paris, M.*; Hale, G. M.*; Shibata, Keiichi; Fukahori, Tokio

Nuclear Data Sheets, 118, p.250 - 253, 2014/04

 Times Cited Count:7 Percentile:39.56(Physics, Nuclear)

Oxygen is one of the most important materials in nuclear applications. However, there are big discrepancies among experimental and evaluated data in $$^{16}$$O($$n,alpha$$) cross section. Also, there are increasing demands for giving uncertainties in evaluated cross section to estimate the margin of integral calculations. We analyzed experimental cross sections with R-matrix theory, and estimated cross sections with their uncertainties. In this analysis, not only the neutron but also an inverse reactions were included. The systematic uncertainties were also considered for each measurement. The resulting cross sections and uncertainties mirror both experimental and theoretical knowledges.

Journal Articles

Theoretical analysis of $$gamma$$-ray strength function for Pd isotopes

Iwamoto, Nobuyuki; Terada, Kazushi*

Nuclear Data Sheets, 118, p.246 - 249, 2014/04

 Times Cited Count:1 Percentile:85.28(Physics, Nuclear)

Gamma-ray Strength Function (GSF) is one of the important components to understand capture reaction process by fast neutrons. The GSF is directly determined by measured data of photonuclear reaction. However, information of the GSF below neutron Binding Energy (BE) is not obtained from those data. In order to fix the GSF below the BE, it is effective to use measured spectrum of $$gamma$$-rays emitted by neutron capture reaction. In this work GSF was evaluated by using $$gamma$$-ray spectra and cross sections of neutron capture reactions for stable Pd isotopes and cross sections of photonuclear reaction for natural Pd. Theoretical analysis was performed by nuclear reaction calculation code CCONE. As a result, we derived GSF which reproduced the both data simultaneously. The cross section and $$gamma$$-ray spectrum for $$^{105}$$Pd calculated on the basis of the GSF show a good agreement with the recently measured data. The cross section decreases from that of JENDL-4.0 by 8% in the keV energy region.

Journal Articles

Remarks on KERMA factors in ACE files

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

Nuclear Data Sheets, 118, p.450 - 452, 2014/04

 Times Cited Count:4 Percentile:55.88(Physics, Nuclear)

KERMA (Kinematic Energy Release in Material) factors are used as response data in order to obtain nuclear heating in nuclear analyses. These data are not directly included in nuclear data libraries and they in ACE (A Compact ENDF) files for the Monet Carlo radiation transport code MCNP are deduced from cross section data for all the reactions in nuclear data libraries with the NJOY code. Many peoples use these data unquestioningly, but little is known concerning fact that most of these data are not always correct. Thus we have examined KERMA factors in the latest official ACE files; those of JENDL-4.0, ENDF/B-VII.1, JEFF-3.1.1, etc. It is found out that a lot of KERMA data in the official ACE files of JENDL-4.0, ENDF/B-VII.1, JEFF-3.1.1 are not always correct.

Journal Articles

Benchmark calculations for reflector effect in fast cores by using the latest evaluated nuclear data libraries

Fukushima, Masahiro; Ishikawa, Makoto; Numata, Kazuyuki*; Jin, Tomoyuki*; Kugo, Teruhiko

Nuclear Data Sheets, 118, p.405 - 409, 2014/04

 Percentile:100(Physics, Nuclear)

35 (Records 1-20 displayed on this page)