Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Calculation of neutron cross-sections on copper-63 and -65

Nakayama, Shinsuke

Journal of Nuclear Science and Technology, 55(6), p.614 - 622, 2018/06

 Times Cited Count:2 Percentile:20.93(Nuclear Science & Technology)

Toward the development of the next version of Japanese Evaluated Nuclear Data Library (JENDL) general-purpose file, we calculate neutron cross-sections on $$^{63,65}$$Cu from 50 keV to 20MeV, which is the incident energy range above the resolved resonance region in JENDL-4.0. A dispersive optical model potential is adopted with a coupled-channel method for interaction between neutron and $$^{63, 65}$$Cu. Direct, pre-equilibrium, and compound processes are taken into account in the calculation. All cross-sections, differential and double-differential cross-sections are consistently calculated with a single set of model parameters. The calculation results reproduce the measured data very well. In addition, disagreement between the calculated and experimental values seen in an integral test for the $$^{63}$$Cu$$(n,alpha)^{60}$$ reaction is improved by using the cross-section data obtained from the present work.

Journal Articles

Evaluation of neutron nuclear data on copper isotopes by a consistent method

Nakayama, Shinsuke

JAEA-Conf 2016-004, p.147 - 152, 2016/09

Copper is an important element relevant to heat sink material for fusion reactors, structural material for accelerator-driven systems, and so on. Therefore, more precise neutron nuclear data on copper isotopes are currently required. In addition, covariance data are also required to estimate uncertainties of various integral quantities obtained from calculation using the nuclear data. Covariance includes correlated uncertainties between different nuclear data, e.g. cross sections of different reactions. In evaluation on $$^{63,65}$$Cu of JENDL-4.0, the cross sections and angular distributions for several reactions were calculated by various computational codes. Towards preparation of covariance data, we evaluated neutron nuclear data on $$^{63,65}$$Cu by a consistent method using the CCONE code.

Journal Articles

Measurement of coherent neutron scattering length with LLL-type interferometry at PNO in JRR-3M

Tomimitsu, Hiroshi; Hasegawa, Yuji*; Aizawa, Kazuya

Journal of the Physical Society of Japan, Vol.70, Supplement A, p.462 - 464, 2001/05

no abstracts in English

Journal Articles

Neutron interferometric measurement of the scattering lengths of W, $$^{63}$$Cu, $$^{65}$$Cu, Cu, $$^{202}$$Hg and Hg

Tomimitsu, Hiroshi; Hasegawa, Yuji*; Aizawa, Kazuya

Physics Letters A, 274(5-6), p.175 - 183, 2000/09

 Times Cited Count:5 Percentile:42.52(Physics, Multidisciplinary)

no abstracts in English

Oral presentation

Evaluation of neutron nuclear data on copper isotopes in fast energy region

Nakayama, Shinsuke

no journal, , 

Toward development of an activation cross section file, we evaluated neutron cross sections on copper isotopes in the incident energy range from 50 keV to 20 MeV. Although copper is important material, the evaluated values of activation cross sections on copper isotopes have not been updated for about thirty years, and some large discrepancies can be seen between the evaluated values and the recently measured ones. In the present study, therefore, we aimed to improve accuracy of activation cross sections. We used the CCONE code for nuclear reaction calculation. Direct component was calculated by the dispersive coupled-channel optical model and the distorted wave Born approximation. Pre-equilibrium and compound components were calculated by the two component exciton model and the Hauser-Feshbach model, respectively. The present evaluation results reproduced the existing measured data better than the evaluated data of JENDL-4.0.

5 (Records 1-5 displayed on this page)
  • 1