Nuclear fuel assembly design and fabrication

Wiesenack, Wolfgang

doi:10.1533/9780857096388.2.203

Cited by 5 publications

(2 citation statements)

References 14 publications

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“…The FA is fabricated and arranged in the form of a 17 x 17 matrix with dimensions of 21.5 cm x 21.5 cm, containing 289 holes for fuel rods, material absorbers, instrument rods, and control rods. Broadly speaking, the FA design consists of a Top Nozzle, Bottom Nozzle, Spacer, fuel rod, and guide thimble tube [9], as illustrated in Figure 1. The specifications for the three types of FA can be seen in Table 1 and Figure 2 The basic information for the SMART reactor design, as shown in Table 2 The highlight of the SMART reactor design is related to the safety features, which consist of passive safety systems, such as the Passive Residual Heat Removal System, Emergency Core Cooling System, and the Reactor and Containment Overpressure Protections, along with multiple safety designs.…”

Section: Smart Reactor Characteristicsmentioning

confidence: 99%

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Usman,

Waris,

Pramuditya

et al. 2024

J. Phys.: Conf. Ser.

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The SMART is a small modular nuclear reactor which has been developed by South Korea’s KAERI, utilizes 4.95% enriched uranium fuel and two types of absorber materials: Gd2O3 - UO2 and Al2O3 - B4C. This research focuses on the neutronic analysis of SMART at the fuel cell and fuel assembly levels using SRAC 2006 with JENDL 3.3 and 4.0 Nuclear Data Libraries. The study aims to compare the neutronic performance of the SMART fuel assembly using these two absorber materials. At the fuel level, three types of enrichment are considered: 2.82%, 3.25%, and 4.95%. Meanwhile, at the fuel assembly level, three types (A, B, and C) are investigated, based on the composition of fuel rods and absorber material rods. The results indicate that the SMART reactor with the KAERI design (enrichment of 4.95% and 3 types of fuel assemblies) can maintain critical conditions for 990 days (equivalent to 3 years) of operation for small modular reactor types. The two types of absorber materials are effective in absorbing excess positive reactivity from the fuel effectively. The use of absorbing materials greatly determines the neutronic characteristics and costs in the construction of nuclear reactors, It can be compared that using 2 absorbing materials can reduce the value of the effective multiplication factor and the infinitive neutron production in the core compared to using 1 absorbing material.

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Section: Smart Reactor Characteristicsmentioning

confidence: 99%

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Usman,

Waris,

Pramuditya

et al. 2024

J. Phys.: Conf. Ser.

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“…In the event further optimisation of the core design (such as through greater enrichment/poison zoning) is unable to reduce rod power history disparities, then a logical solution is to insist on variable channel flow across the core in order to minimise the differences in peak coolant temperatures. The use of variable channel flow is well-demonstrated in LWRs and is currently implemented both in BWRs and in some PWRs (of the VVER variety) through the use of zirconium-alloy boxes that surround the sides of the assembly (to stop cross-flow between assemblies) and through the incorporation of artificial blockages to vary channel flow rates between assemblies (Wiesenack (2012)). Table 7 final design values based on the marine core developed here.…”

Section: Fuel Performancementioning

confidence: 99%

The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion

Peakman

Owen

Abram

2019

Progress in Nuclear Energy

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If international agreements regarding the need to significantly reduce greenhouse gas emissions are to be met then there is a high probability that the shipping industry will have to dramatically reduce its greenhouse gas emissions. For emission reductions from ships greater than around 40% then alternatives to fossil fuels -such as nuclear energy -will very likely be required. A Small Modular Pressurised Water Reactor design has been developed specifically to meet the requirements of a large container ship with a power requirement of 110 MWe. Container ships have a number of requirements -including a small crew size and reduced outages associated with refuelling -that result in a greater focus on design simplifications, including the elimination of the chemical reactivity control system during power operation and a long core life.We have developed a novel, soluble-boron free, low power density core that does not require refuelling for 15 years. The neutronic and fuel performance behaviour of this system has been studied with conventional UO 2 fuel. The size of the pressure vessel has been limited to 3.5 metres in diameter. Furthermore, to ensure the survivability of the cladding material, the coolant outlet temperature has been reduced to 285 • C from 320 • C as in conventional GWe-class PWRs, with a resulting reduction in thermal efficiency to 25%. The UO 2 core design was able to satisfactorily meet the majority of requirements placed upon the system assuming that fuel rod burnups can be limited to 100 GWd/tHM. The core developed here represents the first workable design of a commercial marine reactor using conventional fuel, which makes realistic the idea of using nuclear reactors for shipping.

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Development of manufacturing process and testing of PWR nuclear fuel PIN prototypes

Rianto,

Rahmadi,

Ghufron

et al. 2024

International Conference on Nuclear Science, Technology, and Applications – Iconsta 2022

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Nuclear fuel assembly design and fabrication

Cited by 5 publications

References 14 publications

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion

Development of manufacturing process and testing of PWR nuclear fuel PIN prototypes

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Nuclear fuel assembly design and fabrication

Cited by 5 publications

References 14 publications

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd2O3 – UO2 and Al2O3 – B4C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion

Development of manufacturing process and testing of PWR nuclear fuel PIN prototypes

Contact Info

Product

Resources

About

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries

Neutronics Analysis of SMART Reactor Fuel Cell and Fuel Assemblies with Two Absorber Materials: Gd₂O₃ – UO₂ and Al₂O₃ – B₄C Using SRAC Code and JENDL 3.3 and 4.0 Data Libraries