Fuel Behavior Implications of Reactor Design Choices in Pressurized Water SMRs

Journal Article · Thu Dec 19 00:00:00 EST 2024 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2024.2426416· OSTI ID:2567129

Halimi, Assil ^[1]; Shirvan, Koroush ^[1]

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1. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Small pressurized water reactors (PWRs) can feature boron free operation, natural circulation mode, reduced height assemblies and/or long refueling cycles. This paper attempts to explore core design optimization for each of these design evolutions. In consequence, five core design layouts are developed incorporating boron free operation with continuous control rods insertion, natural circulation with low burnup/low power density design, natural circulation with high burnup/low power density design, forced circulation with standard core power density design, and forced circulation with high power density design. These cores’ performance is compared to a standard 4-loop PWR. The design process aims to improve the fuel cycle cost under safety constraints through core design optimization using CASMO4E/SIMULATE3 reactor physics codes and FRAPCON4.1 fuel performance assessment tool. Core modeling assumes standard 17x17 PWR fuel assemblies loaded with low enriched uranium (LEU) up to 5wt% or LEU+ (i.e., below 10wt% enrichment) pellets with gadolinium oxide (Gd2O3) as the burnable poison. Satisfactory core and fuel performances are obtained for all the designed cores under steady state and considered overpower transients. For low power density operation, long cycle lengths are achieved reaching a 2.5- and a 5-year cycles and peak rod-average burnup is pushed to 83 MWd/kgU. Other cycle lengths are maintained at 18 months. Boron free operation exhibits the ability to achieve longer cycle lengths at the cost of higher peaking factors leading to high local power and fuel temperatures which prevents sizable power uprates and is deemed uneconomical. Fuel assembly height reduction allows coolant velocity retrofit which enables higher core power density without violating structural integrity of the fuel assembly. As a result, a core power density of 123 kW/l is reached where total cladding hoop strain becomes the limiting parameter.

• Research Organization: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: NE0009273
• OSTI ID: 2567129
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 8 Vol. 211; ISSN 0029-5450
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Core Design
Full-Core Fuel Performance
High Burnup Operation
High Power Operation
LEU+
Pressurized Water Reactors
Reactor Design
Small Modular Reactors