Validation of spent nuclear fuel decay heat calculation by a two-step method

Validation of spent nuclear fuel decay heat calculation by a two-step method

In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs). The calculation method is implemented with a lattice code STREAM and a nodal diffusion code RAST-K. One of the features of thi...

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Bibliographic Details
Main Authors: Jaerim Jang, Bamidele Ebiwonjumi, Wonkyeong Kim, Jinsu Park, Jiwon Choe, Deokjung Lee
Format: Article
Language:English
Published: Elsevier 2021-01-01
Series:Nuclear Engineering and Technology
Subjects:
Pressurized water reactor
Isotope inventory
Decay heat
Back-end cycle
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320300231

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http://www.sciencedirect.com/science/article/pii/S1738573320300231

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