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Performance of cemented spent graphene oxide (SGO) for radioactive waste immobilization: A comparative study with spent ion-exchange resins

delete2026-06-17
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PRE
AI
S
Sriyono Sriyono
K
Komar Sutriah
D
Djarot Sulistio Wisnubroto
G
Geni R. Sunaryo
N
Noorshida Mohd Ali
P
Pudji Untoro
D
Dyah Iswantini *
DOI:10.1016/j.pnucene.2026.106492delete
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Abstract

Abstract

En 中文
• Cemented spent graphene oxide (SGO) achieves 3 wt% waste loading and satisfies mechanical acceptance criteria. • Cemented SGO exhibits superior radionuclide retention compared with cemented spent ion-exchange resin (SIER). • Cs-137 shows higher mobility than Co-60, reflecting differences in sorption mechanisms and cesium solubility. • Effective diffusion coefficients confirm stronger immobilization of Co-60 in both cemented waste forms. • The proposed cemented SGO waste form demonstrates robust long-term performance under diffusion-controlled leaching conditions.

Journal

Progress in Nuclear Energy cover
Progress in Nuclear Energy
IF:
3.2
Papers:
5.5K
Citations:
10.0K

Organization

U
universiti pendidikan sultan idris
Scholars:
788
Papers: 631
Citations: 4
P
puspiptek
Scholars:
3
Papers: 3
Citations: 0
I
ipb university
Scholars:
523
Papers: 226
Citations: 0
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