Published 1975 | Version v1
Report Metadata-only

The calculation of the consequences of sodium/fuel interactions with allowance for temperature gradients in the sodium

Creators

  • 1. Kernforschungzentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik

Description

In this paper the state of the code BRENDY is described together with an outlook on its further development. The code is applied to study the effect of various assumptions used in sodium fuel interaction codes in connection with: sodium thermal conductivity, heat transfer during phase B, fuel latent heat of fusion, decoupled heat transfer calculations, incompressible sodium slug

Additional details

Publishing Information

Imprint Title
Second specialist meeting on sodium/fuel interaction in fast reactors, Ispra, 21-23 November 1973
Imprint Pagination
p. 501-521 (paper SNI 2-7).
Report number
EUR--5309

Conference

Title
2. Specialist meeting on sodium/fuel interaction in fast reactors.
Dates
21 Nov 1973.
Place
Ispra, Italy.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
7231272
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
B CODES; FUSION HEAT; HEAT TRANSFER; NUCLEAR FUELS; SODIUM; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY
Descriptors DEC
ALKALI METALS; COMPUTER CODES; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; ENTHALPY; FUELS; METALS; PHYSICAL PROPERTIES; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; TRANSITION HEAT