Temperature sensitivity analysis for an ADS system using different nuclear data libraries

Abstract

SummaryThe aim is to update the evaluated nuclear data library (ENDL) for nuclides used to simulate accelerator driven systems with JEFF3.1, JEFF3.2, and ENDF/B-VII.1. The applied methodology was, first of all, reproduced to 3 ENDL comparing the cross sections with the ADS Nuclear Data Library at 293.6 K. Second, libraries were processed at working temperature at 1200 K in containing fissile/fissionable material and 900 K for the remaining regions. Third, it is performed a criticality calculation at steady state using all temperatures processed at room temperature and working temperature and compared. Results, indicates the suitable ENDL to perform future burnup calculations. | INTRODUCTIONHybrid systems such as ADS, which coupled a proton beam accelerator and a nuclear core, have been studied for transmutation of minor actinides (MA), energy production, and fuel regeneration. 1-3 One of the most interest options of using an ADS is the capability to produce fissile nuclides such as 233 U from the fertile nuclide 232 Th, maintaining a subcritical core.The nuclear engineering department DEN/UFMG has been studying hybrid systems loaded with reprocessed fuel using nonproliferation means, in which the MA and plutonium are all together in the same fuel matrix. Its main purpose is to transmute the amount of MA by high-energy neutrons produced in spallation reactions or in fission chains. [4][5][6] Nevertheless, to perform a more precisely simulation, it is important to use the appropriate nuclear data library, as well as, the operation temperature. Thus, one of the most important issues in nuclear fission is the proper cross section representation, which may be affected by the temperature causing a Doppler effect.

Study of Neutron Yield in Liquid Spallation Target

“…Thus, it is intended to vary the values of L (width) and d (diameter) of the target, as it is expected to estimate the optimal target sizes as a function of the number of neutrons escaping from it. Studies have shown that the number of neutrons escaping from the target increases with increasing target radius and reaches a maximum, after which it decreases with increasing target radius [17].…”

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

“…Sensitivity analysis for the system can assess the importance of numerous parameters to the system responses for all possible situations. Analysis results can provide useful information to reactor design optimization, uncertainty propagation and quantification, and estimating biases of the simulation code and uncertainty, for instance. Especially for MSR, the influence from the coupled physics such as reactivity feedback from temperature or density changes of moving fuel salt is the issue to assess how much sensitive the system response is.…”