Resonance treatment using pin-based pointwise energy slowing-down method

Choi, Sooyoung; Lee, Chang-Ho; Lee, Deokjung

doi:10.1016/j.jcp.2016.11.007

Cited by 64 publications

(28 citation statements)

References 15 publications

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“…To increase the shutdown margin, 21 assemblies are set as control element assemblies and the remaining 16 assemblies are set as WABA assemblies. Figure 12 highlights the positions of the WABA assemblies (W) and the positions available for the CRs (P1‐P5) 22 . Three types of assembly are used for radial LP generation: FA01, FA02, and W presented in Figure 13.…”

Section: Core Design Resultsmentioning

confidence: 99%

“…The STREAM performs lattice physics calculations to generate the cross sections and the form functions of 2D assemblies and the reflector model 17 . The resonance treatment for the cross sections is based on the pointwise energy slowing‐down method (PSM) 22 . In addition, the PSM is applied to R‐BA containing resonant nuclides, and has been verified against the Monte Carlo codes SERPENT2.1.27 and MCS 20‐22 .…”

Section: Core Design Strategymentioning

confidence: 99%

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Conceptual design of long‐cycle boron‐free small modular pressurized water reactor with control rod operation

et al. 2020

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Summary This paper presents a new conceptual design of soluble‐boron‐free small modular pressurized water reactor (SMPWR) core with the following singular features: long operation cycle, axially heterogeneous adjuster control rods, and ring‐type burnable absorbers (R‐BAs) coated on the outside of cladding materials. The core loads 37 Westinghouse‐type 17 × 17 fuel assemblies (FAs) of active fuel height 200 cm and produces 180 MW of nominal thermal power during a cycle length of 1555 effective full power days (EFPDs). Three types of burnable absorbers (BAs) are used to address the excess reactivity and obtain a long cycle: 2 w/o and 8 w/o enriched Gd2O3 integral‐type BA (IBA), natural gadolinium R‐BA, and 80 w/o enriched 10B Al2O3/B4C wet annular burnable absorber (WABA). Two types of 200 cm long axially heterogeneous adjuster control rods are used to control the reactivity and the offset in axial power distribution. The first rod type adopts HfB2 with 80 w/o enriched 10B for the bottom 140 cm and stainless steel for the top 60 cm. The second rod type uses HfB2 (natural boron) for the bottom 100 cm and HfB2 (80 w/o enriched 10B) for the top 100 cm. A detailed safety parameter analysis is conducted to verify the imposed design limits, namely, axial shape index of less than ±0.4, 3D power peaking factor of smaller than 5.09, required shutdown margin of greater than 3000 pcm, and negative isothermal temperature coefficient during the entire reactor operation. It is successfully demonstrated that the proposed novel SMPWR design satisfies all the design limits and the target cycle length of 1500 EFPDs.

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Section: Core Design Resultsmentioning

confidence: 99%

Section: Core Design Strategymentioning

confidence: 99%

Conceptual design of long‐cycle boron‐free small modular pressurized water reactor with control rod operation

et al. 2020

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“…Based on flat nuclide atom density distribution within the fuel rod, collision probabilities could be pre-tabulated as a function of macroscopic total XSs, so they can be calculated in advanced against several typical pin cells. This acceleration strategy has been implemented in the MPACT code [10] and STREAM code [12]. However, the tables are strictly depended on the geometrical mesh of the pin cell.…”

Section: Online Tabulation and Interpolation Methodsmentioning

confidence: 99%

Processing Resonance Self-Shielding Effect of Gadolinia Based on Imptoved Supercell Scheme

Wen

et al. 2021

EPJ Web Conf.

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An improved supercell scheme has been proposed in this paper to efficiently and accurately process resonance self-shielding effect of gadolinia. Resonance effects are classified into global shadowing effect and local effects involving resonance interference, spatial self-shielding effects. Two categories of effects are decoupled and treated respectively based on different 1-D cylindrical pins. Hyperfine group method is applied to obtain multi-group cross sections for each 1-D pin. Afterwards, two categories of effects are coupled based on a correction formula. Because of the low efficiency for Carlvik method to compute collision probabilities in hyperfine group method, online tabulation and interpolation method is developed to accelerate gaining collision probabilities. The proposed scheme is verified against the problems of 3×3 pins with gadolinia rod, VERA 2O assembly with 12 gadolinia rods and VERA 2P with 24 gadolinia rods. The numerical results suggest promising consistence of multi-group cross sections and eigenvalues between the proposed scheme and reference solutions.

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“…The RAST-K model of the BEAVRS reactor core uses four radial nodes and 48 axial nodes per fuel assembly for the nodal diffusion calculation. The two-group cross-sections were calculated as the function of fuel temperature, coolant temperature and density, nuclear fuel burnup and boron concentration cross-section code STREAM [27] for each fuel assembly type with and without control rods.…”

Section: Beavrs Core Modelmentioning

confidence: 99%

A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation

et al. 2020

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A new reactor core multi-physics system addresses the pellet-to-cladding heat transfer modeling to improve full-core operational transient and accident simulation used for assessment of reactor core nuclear safety. The rigorous modeling of the heat transfer phenomena involves strong interaction between neutron kinetics, thermal-hydraulics and nuclear fuel performance, as well as consideration of the pellet-to-cladding mechanical contact leading to dramatic increase in the gap thermal conductance coefficient. In contrast to core depletion where parameters smoothly depend on fuel burn-up, the core transient is driven by stiff equation associated with rapid variation in the solution and vulnerable to numerical instability for large time step sizes. Therefore, the coupling algorithm dedicated for multi-physics transient must implement adaptive time step and restart capability to achieve prescribed tolerance and to maintain stability of numerical simulation. This requirement is met in the MPCORE (Multi-Physics Core) multi-physics system employing external loose coupling approach to facilitate the coupling procedure due to little modification of constituent modules and due to high transparency of coupling interfaces. The paper investigates the coupling algorithm performance and evaluates the pellet-to-cladding heat transfer effect for the rod ejection accident of a light water reactor core benchmark.

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Resonance treatment using pin-based pointwise energy slowing-down method

Cited by 64 publications

References 15 publications

Conceptual design of long‐cycle boron‐free small modular pressurized water reactor with control rod operation

Conceptual design of long‐cycle boron‐free small modular pressurized water reactor with control rod operation

Processing Resonance Self-Shielding Effect of Gadolinia Based on Imptoved Supercell Scheme

A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation

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