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Title: Thermal-hydraulic calculations for the conversion to LEU of a research reactor core

Conference ·
OSTI ID:21113495
 [1]; ; ;  [1]
  1. National Center for Scientific Research 'DEMOKRITOS', 153 10 Aghia Paraskevi (Greece)

The thermal-hydraulic analysis performed for the needs of the conversion of the open pool 5MW Greek Research Reactor (GRR-1) to a pure Low Enrichment (LEU) configuration is presented. The methodology was based on a complete set of neutronic calculations performed for the new core configuration, in compliance with pre-defined Operation Limiting Conditions. The hottest channel analysis approach was adopted, and peaking factors were used to account for fabrication or measuring uncertainties. Calculations were carried out using the numerical codes NATCON, PLTEMP and PARET provided by Argonne National Laboratory (ANL). Two main different classes of conditions were considered, namely i) steady state normal operating conditions and ii) transient cases related to accidental events including reactivity feedback effects. For steady state operating conditions the behaviour of the new configuration was examined both for forced and natural convection cooling modes. Transient calculations considered several initiating events including reactivity insertion accidents (slow or fast reactivity insertion) and total or partial loss-of-flow accidents, i.e. in accordance to guidelines provided by the IAEA for research Reactors. (author)

Research Organization:
Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
OSTI ID:
21113495
Report Number(s):
INIS-US-08N0001; TRN: US08N0017121033
Resource Relation:
Conference: RERTR-2007: 29. international meeting on reduced enrichment for research and test reactors, Prague (Czech Republic), 23-27 Sep 2007; Other Information: Country of input: International Atomic Energy Agency (IAEA); 14 refs, 4 figs, 2 tabs; Related Information: In: 2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting, vp.
Country of Publication:
United States
Language:
English