Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)

Odeh, Faisal Y.; Yang, Won Sik

doi:10.1016/j.anucene.2016.03.011

Cited by 7 publications

(5 citation statements)

References 15 publications

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“…This test facility was designed and constructed to perform both transient and quasi-steady flow instability tests for the NMR. The detailed scaling analysis and design could be referred to our previous work [12,15]. The quasi-steady tests had been performed under various conditions by changing system pressure, core inlet subcooling, core inlet flow resistance coefficient, and core heat power etc.…”

Section: Experiemtnal Stability Mapsmentioning

confidence: 99%

“…A recent research has been performed to investigate the flow instability in a Novel Modular Reactor (NMR) design for low power and low pressure conditions. The NMR developed at Purdue University is a BWR-type small modular reactor design, which relies on natural circulation to provide driving force for both normal operations and accidental management [10][11][12]. In previous research, a natural circulation test facility was scaled and designed from the NMR by using the three-level scaling method.…”

Section: Introductionmentioning

confidence: 99%

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Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor

Shi

Ishii

2017

Annals of Nuclear Energy

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An analytical study based on frequency domain analysis is presented on the flashing-induced flow instability in a natural circulation test facility, which was designed to investigate the flow instability for a BWR-type novel modular reactor (NMR). To address the flashing phenomena at low pressure conditions, such as initial startup transients or accidents, the liquid enthalpy change in the P-T diagram due to reduced hydrostatic head in the riser or chimney was treated as an axially uniform heat flux. Based on the drift flux model, the system transfer function was obtained through small perturbations about the steady state in the frequency domain. The D-partition method was used to determine the neutral stability boundary in the dimensionless stability plane, which was constituted of the subcooling number and phase change number. From the frequency domain analysis, the flashing stability boundary and the density wave oscillations boundary could be predicted. Some parametric studies had been performed on the system pressure and the inlet flow resistance coefficients in the stability analysis. The results showed that the flashing stability boundary was more sensitive to the system pressure than the density wave oscillations. In addition, the theoretical stability boundaries were benchmarked against the experimental stability boundaries from quasi-steady state tests. Although the general stability boundary agreed well with the experiments, certain discrepancies still existed due to the assumptions of thermal equilibrium in current study. In the future, the thermal non-equilibrium conditions including subcooled boiling will be taken into account in the flashing induced stability analysis.

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Section: Experiemtnal Stability Mapsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor

Shi

Ishii

2017

Annals of Nuclear Energy

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“…More than 50 SMR designs are currently under development to satisfy a variety of application requirements [5]. Pressurized water reactors [6], boiling water reactors [7], high-temperature gas-cooled reactors [8], liquid metal reactors [9][10][11], and molten salt reactors [12] are the primary reactor types targeted for SMRs.…”

Section: Introductionmentioning

confidence: 99%

Preliminary Design and Study of a Small Modular Chlorine Salt Fast Reactor Cooled by Supercritical Carbon Dioxide

et al. 2023

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Small modular reactors with power below 300 MW have the advantages of small specific mass, long lifetime, and flexible power supply, and they are suitable for providing power support for small and medium-sized towns with small populations and remote areas without grid coverage. In this paper, a small modular S-CO2-cooled molten salt reactor is proposed, and the design of a 10 MW small modular chlorine salt fast reactor (sm-MCFR) with 20 years of operation without refueling is presented. The neutron feasibility of the S-CO2-cooled small modular chlorine fast reactor is analyzed in terms of neutron energy spectrum, reactivity control, temperature reactivity coefficient, and power distribution. A distinctive feature of the sm-MCFR is the use of chlorine salts with high heavy metal solubility and a hard energy spectrum, allowing the core size to be minimized while maintaining the maximum lifetime. The designed core is about 2.44 m in diameter and 2.24 m in height. Meanwhile, the sm-MCFR uses control drum control as the control system, which can effectively achieve reactivity control without increasing the reactor size. The final optimized sm-MCFR has a negative temperature reactivity coefficient, which is necessary to ensure the safe operation of the reactor.

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“…A global market assessment has predicted that the magnitude of the potential market for SMRs is about 65-85 GWe by the year 2035, provided the economics are competitive [2]. The SMR design concepts that have been proposed can be classified into numerous types such as the pressurized water reactor (PWR) [3][4][5], the boiling water reactor (BWR) [6], the liquid metal cooled fast reactor (LMFR) [7][8][9][10][11][12][13], the gas cooled fast reactor (GFR) [14,15] and the molten salt reactor (MSR) technologies [16,17]. Among these concepts, the liquid metal type lead or lead-bismuth eutectic (LBE) is generally chosen as the coolant for SMRs owing to its superior properties including a low melting point, high boiling point and chemical inertness with air and water.…”

Section: Introductionmentioning

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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Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)

Cited by 7 publications

References 15 publications

Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor

Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor

Preliminary Design and Study of a Small Modular Chlorine Salt Fast Reactor Cooled by Supercritical Carbon Dioxide

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

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