Development of multi-group neutron activation cross-section library from JENDL/AD-2017

Konno, Chikara

JAEA-Conf 2020-001, p.193 - 197, 2020/12

https://doi.org/10.11484/jaea-conf-2020-001

JENDL Activation Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017) was released in 2018. This file includes the data of neutron-induced nuclear reactions for 311 nuclides from 10 eV to 20 MeV. Thus a multi-group neutron activation cross-section library (MAXS/AD-2017) with the same format as MAXS-2015 by Dr. Okumura has been developed from JENDL/AD-2017 with PREPRO 2018 for activation calculations in nuclear facility decommissioning. MAXS/AD-2017 will be converted to ORIGEN libraries and be tested with the JPDR decommissioning data. Then MAXS/AD-2017 will be released.

Neutron capture cross section measurement of minor actinides in fast neutron energy region for study on nuclear transmutation system

Katabuchi, Tatsuya*; Hori, Junichi*; Iwamoto, Nobuyuki; Iwamoto, Osamu; Kimura, Atsushi; Nakamura, Shoji; Shibahara, Yuji*; Terada, Kazushi*; Tosaka, Kenichi*; Endo, Shunsuke; et al.

JAEA-Conf 2020-001, p.5 - 9, 2020/12

https://doi.org/10.11484/jaea-conf-2020-001

A Consideration on nuclear data needs for 1F decommissioning

Fukahori, Tokio

JAEA-Conf 2020-001, p.17 - 20, 2020/12

https://doi.org/10.11484/jaea-conf-2020-001

After 9 years from the accident at TEPCO Fukushima Daiichi Nuclear Power Station, the "on-site" research and development (R&D) situation has been changed into new phase. It can be considered from understanding to predicting by many direct and indirect measurements and analyses. In this presentation, nuclear data needs for 1F decommissioning are revisited according to these situation. The needs for accident evolution characteristics, criticality management, debris storage, waste management, etc. are considered with the view point of R&D on prediction what is going on and will be happened in each stage of decommissioning.

Measurement of total neutron cross section of Niobium-93 at J-PARC MLF ANNRI

Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Toh, Yosuke; Segawa, Mariko; Maeda, Makoto; Tsuneyama, Masayuki*

no journal, , 

Niobium (Nb)-93, which is mono isotope, is one of the material elements to strengthen stainless steel and is used for structural materials of nuclear reactors. Since Nb is also used as an element of superconductor alloys, it has been used in fields such as fusion reactor and accelerator development. Determination of neutron total cross section with high accuracy is therefore required in the field of nuclear technology. The cross sections of Nb were measured by T. Wang (2011), N. J. Drindak (2006) and so on. However, the resonance parameters determined by them have discrepancies up to about 10% each other. In order to determine the more precise values of resonance parameters, transmission measurements were performed to evaluate total cross section of Nb-93 at the ANNRI of MLF in J-PARC in June of 2019. The ANNRI is one of beamlines in MLF, and Germanium gamma-ray detectors and the Liglass neutron detectors are installed to measure nuclear reactions. A target was natural Nb plate of 25 mm 25 mm 10 mm whose size was determined from necessary statistic. Since the target size was big and the thermal-neutron capture cross-section is small (about 1.1 barns), the effect of neutron diffraction was observed in low neutron energy region. When discussing reactions to a single nucleus, the effect of diffraction resulting from crystal structure is unnecessary information. Thus, this effect must be estimated and removed to determine the total cross section as nuclear data for a single nucleus. In this poster, I will present preliminary results of the experiment and the estimated effects of neutron diffraction. This work has been supported in part by Grants-in-Aid for Scientific Research (JP17H01076).