The neutron-induced fission cross sections were simultaneously evaluated for the JENDL-5 library for 233,235U and 239,241Pu from 10 keV to 200 MeV and for 238U and 240Pu from 100 keV to 200 MeV. Evaluation was performed by least-squares fitting of Schmittroth’s roof function to the logarithms of the experimental cross sections and cross section ratios in the EXFOR library. A simultaneous evaluation code SOK was used with its extension to data in arbitrary unit. The outputs of the code were adopted as the evaluated cross sections without any further corrections. The newly obtained evaluated cross sections were compared with the evaluated cross sections in the JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross sections were also validated against the californium-252 spontaneous fission neutron spectrum averaged cross sections, ΣΣ (coupled thermal/fast uranium and boron carbide spherical assembly) neutron spectrum averaged cross sections, and small-sized LANL fast system criticalities. The changes in the obtained evaluated cross sections from those in the JENDL-4.0 library are within 4% (241Pu), 3% (233U, 240Pu), or 2% (235U, 239Pu). The newly evaluated 235U, 238U and 239Pu cross sections agree with the IAEA Neutron Data Standards 2017 within 2% with some exceptions.
Glandular odontogenic cyst （GOC） is rare odontogenic cyst, first described by Gardener et al. in 1988. We report a case of GOC arising in the maxilla. The patient was 57-year-old man who presented with pain and swelling of the right canine region of the maxilla. Panoramic radiography showed a clearly bordered radiolucent region extending from the canine to premolar region of the maxilla. The clinical diagnosis was a radicular cyst of the canine teeth, and enucleation and tooth extraction were performed with the patient under general anesthesia. The histopathological diagnosis was GOC. As of 12 months after discharge, there has been no evidence of recurrence.
A neutron filtering system has been designed and implemented in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC) to bypass the effect of the double-bunch mode of JPARC by molding the incident neutron flux into quasi-monoenergetic neutron beams. Filter assemblies using Fe, Si and Cr as filter materials were analyzed by means of experimental analysis, together with Monte Carlo simulations. The characteristics of the filtered neutron beam are presented and discussed alongside its viability in future applications for neutron cross-section measurements in the keV neutron region.
Activity determination of 241,243Am samples has been performed with two separate methods of calorimetry and gamma-ray spectroscopy. Decay heat measurements of the samples were carried out by using a calorimeter, and activities of the samples were accurately determined with uncertainties less than 0.45%. The primary source of uncertainty in the calorimetric method is the accuracy of available half-life data. Gamma-ray detection efficiencies of a HPGe detector were determined with uncertainties of 1.5% by combining measured efficiencies and Monte Carlo simulation. Activities of the samples were determined with uncertainties less than 2.0% by gamma-ray spectroscopy and were concordant with those of the calorimetry.
