The Development Of One-Dimensional Transport And Burnup Calculation Code System

The FDS(Fusion-Driven Sub-critical System) can realize the transmutation of HLW(High Level Waste),fuel production, energy breeding and tritium production by utilizing the external neutron source to make the reactor operated under the sub-critical state. The burn up calculation is the important part of the study on the conceptual design of nuclear reactor. On the basis of one-dimensional transport calculation, we have given two ways to solve the burnup equation, one is the analytic method (BATEMAN), the other is the numerical method. One-dimensional discrete ordinates neutron transport and bumup calculation code system-BISONC is revised to perform the blanket neutronics analysis. We have promoted the transport library of BISONC to consider the resonance self-shielding effect. The BISONC burnup library is replaced to facilitate the computation of the burnup process with complicated burnup chains. We have made and evaluated the new library (HENDL) which contains 139 kinds of nuclides with 175 groups for neutron and 42 groups for gamma, 15 kinds of neutron reactions and P0-P5 expansion. The revised code which we call BUS-ID is more adaptable to the computation of hybrid reactor for its fuel breeding and the transmutation of the HLW. We have tested the HENDL by evaluations of many modules, such as one-dimensional spherical module of some elements, FBB (Fuel Breeding Blanket) module etc. And we also have optimized the neutronics parameters of DWTB (Dual Waste Transmutation Blanket) module with BUS-ID. The paper is the important part of developing the new code BUS-3D which will realize three dimensional transport computation and numerical method to solve the burnup equations.