Abstract
The source term calculation capability is developed for the high-fidelity neutronics code NECP-X. Generally, a full activation library is used, but the memory requirement is unacceptable for the high-fidelity calculation. In order to minimize the memory requirement during the calculation with very strict conditions, a new generalized activation chain compressed method is proposed based on the influence qualification. One basic compression element is a reaction channel or an isotope, and the influence of every compression element to the final results are qualified. To enlarge the range of application of the new compressed library, an effective method to determine representative problems, which utilizes the neutron spectra and neutron flux, is developed and analyzed. Based on the ENDF-VII.0, EAF-2010 evaluated nuclear library and the influence qualification-based activation library compression method, a new compressed activation library is generated. The VERA-3A problem and the KAIST problem are used to assess the accuracy and the efficiency of the new activation library. 85 measurements of decay heat from decay heat measurement facilities GE-Morris and CLAB are used to validate the decay heat calculation in NECP-X. The results show good accuracy of NECP-X in predicting radiation source term of the spent nuclear fuel and significant memory saving when using new compressed activation library.
Highlights
Radiation source term is a very important parameter for radiation shielding design for nuclear facilities such as fuel storage pools, Spent Nuclear Fuel (SNF) transport systems, spent-fuel interim storage facilities and spent-fuel reprocessing plants
The specification of VERA-3A and KAIST core are presented in Figure 3, which are originally steady-state cases
A new generalized activation chain compressed method to minimize the size of activation library, which will reduce the computational burden and memory requirement, is proposed
Summary
Radiation source term is a very important parameter for radiation shielding design for nuclear facilities such as fuel storage pools, Spent Nuclear Fuel (SNF) transport systems, spent-fuel interim storage facilities and spent-fuel reprocessing plants. With the development of the computers, the whole-core calculations can be performed by the one-step calculation, and pretty precise results can be obtained by using the detailed transmutation chain and geometry description, including the pin-wise pin power distribution, accurate reactivity and sub-pin-wise nuclide inventory. A new generalized activation chain compression method is proposed and the source term capability of NECP-X is developed. A generalized activation chain compression method based on the importance qualification analysis is presented in detailed. A GENERALIZED ACTIVATION CHAIN COMPRESSED METHOD BASED ON INFLUENCE QUALIFICATION
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