Published 1987 | Version v1
Miscellaneous

THTR-300: Comparison of calculated and measured design data of the primary coolant circuit

  • 1. Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.)
  • 2. Hochtemperatur-Kernkraftwerk G.m.b.H. (HKG), Hamm (Germany, F.R.)

Description

no abstract available

Availability note (English)

Available from Deutsches Atomforum e.V., Bonn (Germany, F.R.).

Additional details

Additional titles

Original title (German)
THTR-300: Vergleich von berechneten und gemessenen Auslegungsdaten des Primaerkreislaufs

Publishing Information

Imprint Title
Annual meeting on nuclear technology '87. Proceedings. Session 2: Thermodynamics and fluiddynamics
Imprint Pagination
829 p.
Journal Page Range
p. 129-132.
ISSN
0720-9207

Conference

Title
Annual meeting on nuclear technology.
Dates
2-4 Jun 1987.
Place
Karlsruhe (Germany, F.R.).

Optional Information

Notes
Published in summary form only. Imprint:Jahrestagung Kerntechnik '87. Tagungsbericht. Sektion 2: Thermo- und Fluiddynamik.