Modelling of RBMK-1500 SNF storage casks activation during very long term storage

Narkunas, Ernestas; Smaizys, Arturas; Poškas, Povilas; Ragaisis, V.

doi:10.1016/j.apradiso.2016.06.015

Applied Radiation and Isotopes

2016

DOI: 10.1016/j.apradiso.2016.06.015

|View full text |Cite

Modelling of RBMK-1500 SNF storage casks activation during very long term storage

Ernestas Narkunas

Arturas Smaizys

Povilas Poškas

et al.

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

Supporting

Mentioning

Contrasting

Year Published

2018

2021

Publication Types

Select...

Article4

Relationship

Self Cite1

Independent3

Authors

Journals

Cited by 4 publications

(1 citation statement)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Secondary gamma emissions due to (n, γ) reactions and bremsstrahlung, and emissions from neutron-activated steel components of SF assemblies were not taken into account. Neutron activation of the container components was deemed insignificant [20].…”

mentioning

confidence: 99%

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

et al. 2021

Self Cite

View full text Add to dashboard Cite

The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. However, the risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with RBMK-1500 SF. All calculations were performed using the SCALE computer codes system. The modeling results show that the overall shielding properties of the CONSTOR® RBMK-1500 container containing the same neutron and gamma sources are better than those of the CASTOR® RBMK-1500 container. During an extended storage period (from 50 to 300 years), the total dose rate would decrease considerably and the dose rate due to neutrons would become dominant for both containers.

show abstract

mentioning

confidence: 99%

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

et al. 2021

Self Cite

View full text Add to dashboard Cite

show abstract

Preparation and characterization of Portland cement pastes with Sm2O3 microparticle additions for neutron shielding applications

Florez

Colorado

Giraldo

et al. 2018

Construction and Building Materials

View full text Add to dashboard Cite

Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel

Narkunas

Smaizys

Poškas

et al. 2021

Nuclear Engineering and Technology

View full text Add to dashboard Cite

scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.

Contact Info

hi@scite.ai

334 Leonard St

Brooklyn, NY 11211

Blog Terms and Conditions API Terms Privacy Policy Contact Cookie Preferences Do Not Sell or Share My Personal Information

Made with 💙 for researchers

Part of the Research Solutions Family.

Modelling of RBMK-1500 SNF storage casks activation during very long term storage

Cited by 4 publications

References 4 publications

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

Preparation and characterization of Portland cement pastes with Sm2O3 microparticle additions for neutron shielding applications

Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel

Contact Info

Product

Resources

About