2018
DOI: 10.1016/j.anucene.2018.07.045
|View full text |Cite
|
Sign up to set email alerts
|

Explicit decay heat calculation in the nodal diffusion code DYN3D

Abstract: • Microscopic cross-sections are pre-generated for each isotope and reaction type. • Local concentrations of over 1000 nuclides are calculated using micro depletion. • Time-dependent decay heat power is calculated by summing the isotopic decay heat contribution. • The method is implemented in nodal code DYN3D and verified against Serpent 2.

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1

Citation Types

0
1
0

Year Published

2019
2019
2021
2021

Publication Types

Select...
5

Relationship

0
5

Authors

Journals

citations
Cited by 6 publications
(1 citation statement)
references
References 16 publications
0
1
0
Order By: Relevance
“…burnup calculation and are important for reactor decay heat release calculations. Especially for Cs134m0, it is one of the main decay heat contributors of UOX fuels in long-term after reactor shutdown [32]. e updated relative uncertainty of Zr95m0 IFY is 16.1% while Cs134m0 and Mo95m0 have their relative uncertainties of 38.4% and 65.7%, respectively.…”
Section: Consider the Preservation Of Probability; The Relation Between Random Variables In Original Domain And Logarithmic Domain Is Formentioning
confidence: 99%
“…burnup calculation and are important for reactor decay heat release calculations. Especially for Cs134m0, it is one of the main decay heat contributors of UOX fuels in long-term after reactor shutdown [32]. e updated relative uncertainty of Zr95m0 IFY is 16.1% while Cs134m0 and Mo95m0 have their relative uncertainties of 38.4% and 65.7%, respectively.…”
Section: Consider the Preservation Of Probability; The Relation Between Random Variables In Original Domain And Logarithmic Domain Is Formentioning
confidence: 99%