Published 2007 | Version v1
Book

Summarizing of development results for reactor ceramic rod fuel elements of Nuclear Rocket Propulsion (NRP), Nuclear Power Propulsion Facility (NPPF), and Nuclear Hydrodynamical Propulsion Facility (NHPF)

  • 1. Inst. Atomnoj Ehnergii, Kurchatov (Kazakhstan)

Description

In reactors both the space nuclear facilities (Nuclear Rocket Propulsion and Nuclear Power Propulsion Facility) and the ground-base Nuclear Hydrodynamical Facility of the same cell-free ceramic fuel elements type in the form double-blade involute rods with length 100 mm have been intended for apply. In the paper the summary of results on material testing for rod ceramic fuel elements condition after its trials in H2 gas-cooled channels of EWG-1M reactor and IRGIT reactor and N2 gas-cooled channels of EWG-1 reactor is presented

Part of:
Abstracts of 6. International conference 'Nuclear and Radiation Physics'

Additional details

Additional titles

Original title (Russian)
Обобщение результатов реакторной отработки стержневых керамических твэлов для реакторов ЯРД, ЯЭДУ и ЯГДУ

Publishing Information

Publisher
Inst. Yadernoj Fiziki NYaTs RK
Imprint Place
Almaty (Kazakhstan)
ISBN
9965-675-37-6
Imprint Title
Abstracts of 6. International conference 'Nuclear and Radiation Physics'
Imprint Pagination
726 p.
Journal Page Range
p. 344-345

Conference

Title
6. International conference on Nuclear and Radiation Physics
Original Conference Title
6. Mezhdunarodnaya konferentsiya 'Yadernaya i Radiatsionnaya Fizika'
Dates
4-7 Jun 2007
Place
Almaty (Kazakhstan)

Optional Information