LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors

Zhou, Shengcheng; Wu, Hongchun; Cao, Liangzhi; Zheng, Youqi; Huang, Kai; He, Maogang; Li, Xunzhao

doi:10.1016/j.nucengdes.2014.07.027

Cited by 32 publications

(9 citation statements)

References 8 publications

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“…In the subcritical core, the neutron transport calculation coupled with the burnup calculation is performed by using LAVENDER, a new code developed specially for the design and analysis of ADS (Zhou et al, 2014). The 24 groups cross sections are homogenized and collapsed based on the data from ENDF/B-VI.0.…”

Section: Methodsmentioning

confidence: 99%

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Zhou

Zheng

et al. 2015

Nuclear Engineering and Design

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Section: Methodsmentioning

confidence: 99%

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Zhou

Zheng

et al. 2015

Nuclear Engineering and Design

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“…The System for Advanced Reactor Analysis code system at Xi'an Jiaotong University(SARAX) [34] was used for the neutronics analysis, which included the neutron transport, power profile, nuclide burnup, control rod worth, core reactivity coefficients, and the kinetic parameters calculations. The SARAX code system is comprised of four main components: TULIP, LAVENDER [35], DAISY [36] and COLEUS. The TULIP code generates 26-group region-dependent homogenized cross sections by using the ENDF/B-VII.0 library [37].…”

Section: Computational Approachesmentioning

confidence: 99%

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

et al. 2020

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In this study, a conceptual design was developed for a lead-bismuth-cooled small modular fast reactor SPARK-NC with natural circulation and load following capabilities. The nominal rated power was set to 10 MWe, and the power can be manipulated from 5 MWe to 10 MWe during the whole core lifetime. The core of the SPARK-NC can be operated for eight effective full power years (EFPYs) without refueling. The core neutronics and thermal-hydraulics design calculations were performed using the SARAX code and the natural circulation capability of the SPARK-NC was investigated by employing the energy conservation equation, pressure drop equation and quasi-static reactivity balance equation. In order to flatten the radial power distribution, three radial zones were constructed by employing different fuel enrichments and fuel pin diameters. To provide an adequate shutdown margin, two independent systems, i.e., a control system and a scram system, were introduced in the core. The control assemblies were further classified into two types: primary control assemblies used for reactivity control and power flattening and secondary control assemblies (with relatively smaller reactivity worth) used for power regulation. The load following capability of SPARK-NC was assessed using the quasi-static reactivity balance method. By comparing three possible approaches for adjusting the reactor power output, it was shown that the method of adjusting the coolant inlet temperature was viable, practically easy to implement and favored for the load following operation.

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“…A new design of ADS transmuter named HEIT was proposed . The core configurations are illustrated in Figure .…”

Section: Calculation Modelsmentioning

confidence: 99%

“…In the depletion calculation, the calculation of isotopic composition is evaluated with the Transmutation Trajectory Analysis algorithm. The detailed information of neutronic analysis was described in previous studies .…”

Section: Calculation Modelsmentioning

confidence: 99%

Reactor core transient analysis of an innovative high-level nuclear waste transmuter with metal fuel

Zheng

Cao

et al. 2017

Int. J. Energy Res.

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Summary For the sustainable development of nuclear energy, reducing high‐level nuclear wastes in spent fuels discharged from commercial nuclear power plants is very important. Partitioning and transmutation of minor actinides from these spent fuels are critical for the effective disposal of high‐level wastes. However, transmutation in current operational reactors is not efficient and brings some safety problems. Therefore, a dedicated accelerator‐driven subcritical transmuter named highly efficient industrial transmuter (HEIT) was newly proposed to solve the problems. This system utilizes the uranium‐free metallic dispersion fuel and is of high power density. This paper focuses on the transient analysis of HEIT to prove that it is feasible for the future nuclear industry. Temperatures, cladding stresses, and cumulative creep damage fractions are analyzed. Furthermore, the burnup dependence is also investigated. Three typical transients including the unprotected loss of flow, the beam overpower (BOP), and the unprotected transient overpower are evaluated. Numerical results conclude that in the reactivity insertion transient and the BOP transient, this new system exhibits excellently in safety. However, the shut‐down system is required in flow loss case which lasts more than half an hour. The safety margin changes with core depletion. For unprotected loss of flow, the end of lifetime case is the most important one to care. While for BOP and unprotected transient overpower, both the beginning and end of lifetime should be accommodated. The conclusions will be useful in the future design of HEIT and similar systems. Copyright © 2017 John Wiley & Sons, Ltd.

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LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors

Cited by 32 publications

References 8 publications

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

Reactor core transient analysis of an innovative high-level nuclear waste transmuter with metal fuel

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