Published 1993 | Version v1
Report Open

IGORR 3: Proceedings of the 3. meeting of the International Group On Research Reactors

Description

Of the Research and development needs identified at IGORR-I and IGORR-II, several topics have been investigated and reported on by members. These results are listed, and were shared through IGORR and through the normal publication routes: Thermal-hydraulic tests and correlations ; Corrosion tests and analytical models; Fuel plate fabrication; Fuel plate stability; Fuel irradiations; Structural materials irradiation tests; Instrumentation upgrading and digital control systems;Man-machine interface. Some of the research issues previously identified still need to be addressed: Multidimensional kinetic analysis for small cores; Burnable poison irradiation tests; Neutron guide irradiation tests; Cold source materials irradiation tests; Cold source liquid nitrogen tests; Cold source liquid hydrogen-H2O reaction. Some other R and D needs identified during this workshop are also listed: Accident and safety analysis codes and benchmarks IGORR members will be asked to supply and share information on the methods they use; Thermophysical properties of D20 liquid and vapor (Riso has prepared a report on this, with 150 references, and will publish a heavy water handbook); Chemical and other energy release from core melt ; Fission product release from a molten MTR core; Thermal conductivity of irradiated fuel meat; Tests of cryogenic circulators for single-phase forced convection cold source; Flow blockage tests

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
368 p.
Report number
INIS-XA-C--025

Conference

Title
3. meeting of the International Group On Research Reactors
Acronym
IGORR 3
Dates
30 Sep - 1 Oct 1993
Place
Ibaraki (Japan)

Optional Information

Notes
Refs, figs, tabs