Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor
- 作者: Vityuk V.A.1, Vurim A.D.1, Kotov V.M.1, Pakhnits A.V.1
-
隶属关系:
- Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
- 期: 卷 120, 编号 5 (2016)
- 页面: 323-327
- 栏目: Article
- URL: https://journals.rcsi.science/1063-4258/article/view/247721
- DOI: https://doi.org/10.1007/s10512-016-0138-3
- ID: 247721
如何引用文章
详细
This article is devoted to the development and testing of a new approach to the determination and prediction of the power parameters of tests of model fuel assemblies in the IGR reactor. A method based on the establishment of a relation between the thermophysical and power parameters of fuel assemblies is proposed. The results of experiments performed as part of the preparation of the fuel assemblies for the tests are presented. The power release in fuel assemblies and a relation between the power parameters of IGR and fuel assemblies at different levels of power release in the reactor are determined. The results obtained are used to determine the IGR operating regime in tests with melting of the fuel assemblies.
作者简介
V. Vityuk
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
哈萨克斯坦, Kurchatov, Eastern Kazakhstan Region
A. Vurim
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
哈萨克斯坦, Kurchatov, Eastern Kazakhstan Region
V. Kotov
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
哈萨克斯坦, Kurchatov, Eastern Kazakhstan Region
A. Pakhnits
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
哈萨克斯坦, Kurchatov, Eastern Kazakhstan Region
补充文件
