Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor
- Авторлар: Vityuk V.A.1, Vurim A.D.1, Kotov V.M.1, Pakhnits A.V.1
-
Мекемелер:
- Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
- Шығарылым: Том 120, № 5 (2016)
- Беттер: 323-327
- Бөлім: Article
- URL: https://journals.rcsi.science/1063-4258/article/view/247721
- DOI: https://doi.org/10.1007/s10512-016-0138-3
- ID: 247721
Дәйексөз келтіру
Аннотация
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.
Авторлар туралы
V. Vityuk
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
Қазақстан, Kurchatov, Eastern Kazakhstan Region
A. Vurim
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
Қазақстан, Kurchatov, Eastern Kazakhstan Region
V. Kotov
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
Қазақстан, Kurchatov, Eastern Kazakhstan Region
A. Pakhnits
Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan
Email: j-atomicenergy@yandex.ru
Қазақстан, Kurchatov, Eastern Kazakhstan Region
Қосымша файлдар
