Advanced nuclear systems are expected to use Pu-containing nuclear fuel alongside Minor Actindes (MAs). Accelerator-Driven System (ADS) is a proposed sub-critical advanced nuclear system to lessen the current amount of MAs by means of nuclear transmutation into short-lived or even stable nuclei. The effect of the current nuclear data uncertainty to the criticality assessment of ADS facilities...
Microscopic calculation is one of the effective approaches to complement nuclear data due to its prediction power, firmly based on knowledge of the nuclear physics. To estimate the fission fragment yields (FFY), we suggest a theoretical model composed of the Metropolis random-walk method and microscopic calculations in which the potential energy surface (PES) is deduced from the mean-field...
We are working on a combination of nuclear reaction calculation code CCONE and machine learning libraries to generate and improve the accuracy of nuclear data. In this presentation, we will show an example of optimizing the parameters of the optical potential to reproduce elastic and inelastic scatterings of neutron-54Fe. The elastic scatterings and inelastic scatterings to the first excited...
Small-angle X-ray scattering (SAXS) measurements for cement paste samples have been conducted in order to obtain the time-evolution of nanostructure under the cement hydration process. In the measurements, it is important to avoid drying the cement paste because the SAXS profile of cement paste is affected by drying. By combining a sample cell, a laboratory-based SAXS instrument in Hokkaido...
The elastic scattering reaction cross section data commonly show smaller in backward angles compared to those of forward angles when the energy of incident neutron is high. However, in a high neutron flux field, such as fusion reactor, the effect of back-scattering reaction cross section is becoming not negligible on the calculation result. Until now, there were differences reported between...
We reported that energy distribution data for secondary gammas from the capture reaction of a lot of nuclei in TENDL-2017 had no high-energy gamma peaks, which other nuclear libraries have, at the IAEA FENDL meeting in 2018 [1, 2]. It caused drastically small damage energy production cross sections at incident neutron energies below a few keV. In the process of JENDL development we examined...
For accurate prediction of neutronic characteristics for accelerator-driven systems (ADS) and a source term of spallation neutrons for reactor physics experiments for the ADS at Kyoto University Critical Assembly (KUCA), we have launched an experimental program to measure nuclear data on ADS using the Fixed Field Alternating Gradient (FFAG) accelerator at Kyoto University. As part of this...
The neutron capture cross section of Re-185 in keV region is important in the various fields such as astrophysics and nuclear data. There are limited number of experimental data currently available, most of which are with large uncertainties. In this work, Time-of-Flight measurement of neutron capture cross sections of Re-185 was carried out by using 3MV Pelletron accelerator at Laboratory for...
Cross sections of large angle scattering reaction in nuclear data are commonly smaller than those of forward scattering when energy of an incident neutron is high. However, in a high intensity neutron field, such as fusion reactor, contribution of cross sections of large angle scattering is not negligible on calculation results. Actually, difference between experimental and calculated values...
TKE (Total Kinetic Energy) of fission fragments is the main source of energy (Q-value) released by fission. Therefore, it is important to understand deeply behavior of the TKE in the nuclear fission of uranium, plutonium, and so on from the viewpoint of nuclear power utilizationand to understand the fission process as a basic research. From the experimental results, it is known that the TKE...
In the material integrity test of fusion reactors, neutron irradiation and cooling are repeatedly performed. In the test, it is indispensable to obtain the neutron fluence by some method. Commonly, Nb foil is used for neutron flux measurement, however one Nb foil cannot record a long irradiation period of about one year, because the half-life of produced RI is about 10 days. Relative...
Nuclear fission plays an essential role in nuclear reactors and the r-process nucleosynthesis, which produces heavy elements like gold and uranium via the fission recycling process. Fission fragments of superheavy nuclei can be the seed nuclei of the r-process. However, there has been considerable ambiguity among theoretical predictions for the fission yields of superheavy nuclei. For a more...
Soft errors caused by cosmic-ray have been recognized as a possible major threat to the operation of advanced semiconductor devices on the ground level. The soft error is caused by an upset of memory information induced by the energy deposition in semiconductor devices by energetic ionizing radiation. Recently, the soft errors induced by cosmic-ray muon have received much attention because of...
At RIKEN, new beam line of generating $^{211}$At for targeted alpha therapy is being constructed. Astatine-211 is produced via the $^{209}$Bi($\alpha$, 2n)$^{211}$At reaction at the beam line. The energy of incident α beam is chosen to be 7.2 MeV/u to avoid producing $^{210}$Po, a toxic nucleus. For the radiation shielding of the new beam line, the neutron production thick target yields were...
Thermal neutron scattering law data were calculated for the heavy water molecule toward the fifth version of the Japanese evaluated nuclear data library, JENDL-5. The scattering laws for deuterium and oxygen atoms were computed using the molecular dynamics simulation. The simulations have been performed in the temperature range from 283.6 K to 600 K. The scattering law data have been evaluated...
We formulate a computational method to evaluate the overlap integral of the shell-model and cluster-model wave functions. The framework is applied to the system of the core plus two neutrons, and the magnitude of the overlap of the shell-model configuration (core + n + n) and the di-neutron cluster one (core + 2n) is explored.We have found that the magnitude of the overlap integral is...
In recent years, BNCT, a new radiation therapy for cancers, has attracted attention. A boron compound that can accumulate only in cancer cells is administered into tumor cells in a human body and irradiated with low-energy neutrons. Then 10B and low-energy neutron cause a (n,α) reaction to kill only the cancer cells with produced charged particles. In BNCT epi-thermal neutrons are used aiming...
Recently, Boron Neutron Capture Therapy (BNCT) has been attracting more and more attention as a new type of radiation therapy. BNCT is a method for cancer treatment by irradiating tumor cells with the low-energy neutrons from outside of the human body after accumulating boron in the tumor cells. This therapy can selectively kill tumor cells suppressing the damage of normal cells. In BNCT, it...
Monte Carlo particle transport code PHITS uses nuclear data with A Compact ENDF (ACE) format to simulate nuclear reactions. The current PHITS has only a limited functionality to display data given in ACE, and many of users do their work without knowing nuclear reaction cross-sections. To improve this situation, i have developed a functionality to display cross-sections, including...
