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Nuclear waste attributes of near-term deployable small modular reactors

Journal Article · · Nuclear Engineering and Technology
 [1];  [1];  [2]
  1. Argonne National Laboratory (ANL), Argonne, IL (United States)
  2. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
The nuclear waste attributes of near-term deployable SMRs were assessed using established nuclear waste metrics, which are the DU mass, SNF mass, volume, activity, decay heat, radiotoxicity, and decommissioning LLW volumes. Metrics normalized per unit electricity generation were compared to a reference large PWR. Three SMRs, VOYGR, Natrium, and Xe-100, were selected because they represent a range of reactor and fuel technologies and are active designs deployable by the decade’s end. The SMR nuclear waste attributes show both some similarities to the PWR and some significant differences caused by reactor-specific design features. The DU mass is equivalent to or slightly higher than the PWR. Back-end waste attributes for SNF disposition vary, but the differences have a limited impact on long-term repository isolation. SMR designs can vary significantly in SNF volume (and thus heat generation density). However, these differences are amenable to design optimization for handling, storage, transportation, and disposal technologies. Nuclear waste attributes from decommissioning vary depending on design and decommissioning technology choices. Given the analysis results in this study and assuming appropriate waste management system and operational optimization, there appear to be no major challenges to managing SMR nuclear wastes compared to the reference PWR.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2396303
Alternate ID(s):
OSTI ID: 2475977
Report Number(s):
INL/JOU--24-79476-Rev000
Journal Information:
Nuclear Engineering and Technology, Journal Name: Nuclear Engineering and Technology Journal Issue: 3 Vol. 56; ISSN 1738-5733
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (3)

Short design descriptions of other systems of the HTTR journal October 2004
Neutronics characteristics of a 165 MWth Xe-100 reactor journal February 2020
PRISM: A Competitive Small Modular Sodium-Cooled Reactor journal May 2012

Figures / Tables (9)