Published 1987 | Version v1
Book

Heat transfer investigations for spent fuel assemblies in a dry cask

  • 1. VEB Kernkraftwerk Bruno Leuschner, Greifswald (German Democratic Republic)

Description

For studying the heat transfer processes and predicting the maximum spent fuel element surface temperature in a spent fuel assembly (SFA) transported in a dry cast, model experiments have been performed with a gas filled model cask containing a simplified electrically heated model of a WWER-type SFA with 90 fuel elements. The temperature distribution of the SFA model is measured for different heat rates under vacuum in the model cask, and under normal pressure and overpressure (0.1-0.7 MPa) for several cooling gases (air, argon, helium) in order to separately investigate heat transfer processes by radiation and convection/conduction. The results were compared with the calculations. Computer programs as well as simplified calculation methods for temperature prediction were developed and checked. The results obtained are also useful for thermal analyses in the field of the dry storage of SFAs in a cask or a can. (author)

Part of:
Packaging and transportation of radioactive materials (PATRAM '86)

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020087-7
Imprint Title
Packaging and transportation of radioactive materials (PATRAM '86)
Imprint Pagination
634 p.
Series
Proceedings series.
Journal Page Range
v. 1 p. 247-259.

Conference

Title
International symposium on the packaging and transportation of radioactive materials.
Dates
16-20 Jun 1986.
Place
Davos (Switzerland).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
18057113
Subject category
S42: ENGINEERING; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
CASKS; COMPUTER CODES; CONVECTION; COOLING; DRY STORAGE; EXPERIMENTAL DATA; FUEL ASSEMBLIES; FUEL ELEMENTS; GASES; PRESSURE DEPENDENCE; RADIANT HEAT TRANSFER; RESEARCH PROGRAMS; SPENT FUELS; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTION
Descriptors DEC
CONTAINERS; DATA; ENERGY SOURCES; ENERGY TRANSFER; FLUIDS; FUELS; HEAT TRANSFER; INFORMATION; MATERIALS; NUCLEAR FUELS; NUMERICAL DATA; REACTOR COMPONENTS; REACTOR MATERIALS; STORAGE

Optional Information

Notes
7 refs, 10 figs.
Secondary number(s)
IAEA-SM--286/72.