Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
KHNP recently has obtained the approval for the commercialization of the modified 37-element (or 37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of the main issues for approval was the burnup limit. Due to CANDU design and neutronic characteristics, there...
Main Author: | Eun-ki Lee |
---|---|
Format: | Article |
Language: | English |
Published: |
Elsevier
2021-03-01
|
Series: | Nuclear Engineering and Technology |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573320302643 |
Similar Items
-
OPTIMISATION OF MONTE CARLO BURNUP SIMULATIONS
by: Dufek Jan, et al.
Published: (2021-01-01) -
Monte Carlo with fuel burnup method for the ENHS benchmark calculations
by: Milošević Miodrag 1, et al.
Published: (2003-01-01) -
Development of a Reduced Order Model for Fuel Burnup Analysis
by: Christian Castagna, et al.
Published: (2020-02-01) -
Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code
by: L. Mercatali, et al.
Published: (2021-09-01) -
Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR
by: Kępisty Grzegorz, et al.
Published: (2015-09-01)