Skip to main navigation Skip to search Skip to main content

A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels

  • Sohee Cha
  • , Kwangheon Park
  • , Mun Oh Kim
  • , Jae Hun Ko
  • , Jin Hyun Sung

Research output: Contribution to journalArticlepeer-review

5 Citations (Scopus)

Abstract

Spent fuels (SFs) are stored in a storage pool after discharge from nuclear power plants. They can be transferred to for the further processes such as dry storage sites, processing plants, or disposal sites. One of important measures of SF is the burnup. Since the radioactivity of SF is strongly dependent on its burnup, the burnup of SF should be well estimated for the safe management, storage, and final disposal. Published papers about the methodology for the burnup estimation from the known activities of important radioactive sources are somewhat rare. In this study, we analyzed the dependency of the burnup on the important radiation source activities using ORIGEN-ARP, and suggested simple correlations that relate the burnup and the important source activities directly. A burnup estimation equation is suggested for PWR fuels relating bur-nup with total neutron source intensity (TNSI), initial enrichment, and cooling time. And three burnup estimation equations for major gamma sources,137Cs,134Cs, and154Eu are also suggested.

Original languageEnglish
Pages (from-to)303-313
Number of pages11
JournalJournal of Nuclear Fuel Cycle and Waste Technology
Volume21
Issue number3
DOIs
Publication statusPublished - Sept 2023

Bibliographical note

Publisher Copyright:
© 2023, Korean Radioactive Waste Society. All rights reserved.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

  1. SDG 7 - Affordable and Clean Energy
    SDG 7 Affordable and Clean Energy

Keywords

  • Burnup estimation
  • Cooling time
  • Enrichment
  • Neutron and gamma sources
  • Spent nuclear fuel

Fingerprint

Dive into the research topics of 'A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels'. Together they form a unique fingerprint.

Cite this