Validation of SARAX code system using the SFR operational tests

Du, Xianan; Zheng, Youqi; Wang, Yongping; Zhai, Zian; Zhou, Hang

doi:10.1016/j.anucene.2020.107744

Cited by 4 publications

(1 citation statement)

References 15 publications

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“…The SARAX code consists of four parts: The cross-sections generation module TULIP [7], the reactor steady-state analysis module LAVENDER [8], the reactor transient analysis module DAISY [9], and the neutron spectrum modification and shielding design module HYDRA [10]. Many verification and validation works have been conducted during the code development stage, such as the OECD/NEA sodium-cooled fast reactors benchmark, the JOYO MK-I zero power experiments, and several assembly layouts of zero power physics reactor (ZPPR) series experiments [11][12][13].…”

Section: Introductionmentioning

confidence: 99%

Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation

Zheng

et al. 2021

Energies

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Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-group cross-sections generation. Therefore, the purpose of this paper is to compare the influence whether the angular dependence on neutron flux is considered in the calculation of few-group cross sections for the reactivity effect calculation. In the study, the 1-D SN finite difference neutron transport equation solver was implemented in the TULIP of SARAX code system so that the high-order neutron flux could be obtained. Meanwhile, the improved Tone’s method was also applied. The numerical results were obtained based on three experimental FR cores, the JOYO MK-I core, ZPPR-9 core, and ZPPR-10B core. Both control rod worth and sodium void reactivity were calculated and compared with the measurement data. By summarizing and comparing the results of 46 cases, significant differences were found between different consideration of the neutronic analysis. The consideration of angular dependence on neutron flux distribution in the few-group cross-sections generation was beneficial to the neutronic design analysis of FR, especially for the reactivity effect calculation.

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