학술논문
DEVELOPMENT OF A THERMAL HYDRAULIC MODEL FOR THE VERSATILE TEST REACTOR USING THE CTF SUBCHANNEL CODE
Document Type
Conference Paper
Author
Source
In: Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 , Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021, 2021, :2274-2283)
Subject
Language
English