Saerom Kwon

Neutronics of SiC-LiPb High Temperature Blanket for Tritium Production

Abstract This study evaluates tritium production and breeding behavior in a LiPb blanket module with the neutron transport code MCNP using nuclear cross-section data from FENDL-2.1 libraries. The calculation results suggest that a sufficient tritium breeding ratio (TBR) can be obtained in the SiC-LiPb blanket concept and therefore a proper integral experiment on LiPb with DT neutrons can be planned for a small test module. Also, TBR, neutron shielding and nuclear heating in the module were evaluated. With the results of TBR and results from actual neutron generation devices, we have proposed a plan for an integral experiment with a measurable tritium amount.

Lead Benchmark Experiment with DT Neutrons at JAEA/FNS

Abstract A new benchmark experiment on lead with DT neutrons was designed and carried out with a large lead assembly covered with Li2O blocks at JAEA/FNS to validate nuclear data of lead for measurement of reaction rates without impact of background neutrons. The experiment was analyzed by using the MCNP5-1.40 code with the latest nuclear data libraries, ENDF/B-VII.1, JEFF-3.2 and JENDL-4.0. The calculated reaction rates underestimated the measured ones with the depth. Moreover, the tendencies of C/Es were different among the nuclear data libraries. In order to find out the reasons of the differences, we examined reaction cross-sections of lead in the nuclear data libraries in detail. The potential reactions to cause the underestimation issue of the calculated reaction rates were indicated through this study.

Conceptual study on production of 99 Mo/ 99m Tc in plan of advanced fusion neutron source (A-FNS)

A plan of an advanced fusion neutron source (A–FNS) using the d-Li reaction is being developed at Rokkasho site of National Institutes for Quantum and Radiological Science and Technology (QST). Although the main objective of the A–FNS facility is fusion material irradiation, applications using fusion neutrons are being investigated. We calculated production yields of Mo, which is the parent nuclide of Tc and important in medical diagnosis, as one of the applications in order to evaluate the potential of the A–FNS. A modified IFMIF test cell design for the A–FNS was used to calculate the production of Mo by using the McDeLicious–11 code and FENDL–3.1b and FENDL/A–3.0 nuclear data libraries. At a position on the surface of a high-flux test module, we estimated the activity of Mo to be 83 TBq, which was obtained from the Mo(n,2n)Mo reaction in a 2-day irradiation, for a 100%-enriched Mo sample of 250 g. This amount covers almost all of the demand for Mo in Japan per week. The use of a natural molybdenum sample is also a promising candidate as an inexpensive Mo production method, because the Mo(n,γ)Mo reaction has large capture cross sections in the resonance energy region.

Evaluation of Tritium Production in LiPb Blanket System Using Neutrons Analysis

Tritium production in LiPb blanket was evaluated by neutronics analysis with Monte Carlo code, MCNP using nuclear cross-section data from the FENDL-2.1 libraries. The result suggests the sufficient TBR (Tritium Breeding Ratio) can be obtained without using additional neutron multiplier such as beryllium. Based on the calculation, a plan for the integral experiment of a small LiPb system to verify it with our DD fusion neutron beam source was made. An integral experiment on LiPb with DD neutrons properly, transport and absorption of the neutron in a small test module was evaluated.