El Salim

Technical specifications, photos, nearby jobs, and satellite map for El Salim.

Reactor Data

Research Reactors

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Research and test reactors, critical assemblies and prototypes at this site, as listed in the IAEA Research Reactor Database: type, thermal power, first criticality, shutdown date, current status and what each is used for.
2 reactors: 2 operational.
Reactor Type Thermal Power First Criticality Shutdown Status Used For
ES-SALAM Heavy Water 15 MWt 1992-02-17 Operational isotope production, neutron scattering, neutron radiography, activation analysis, neutron capture therapy, teaching, training
AURES-1 Subcrit Operational teaching, training
Source: IAEA Research Reactor Database (RRDB), as of 2026-10-13.

Working Here

Per Diem Rates FY 2026

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Per diem covers lodging and meals & incidental expenses (M&IE) for government and contractor travel near this facility. Rates are from the U.S. State Department foreign per diem tables for FY 2026.
$172
Lodging/Night
$109
M&IE/Day
$281
Total/Day
Algeria: rate for locations the State Department does not list separately
U.S. Department of State foreign per diem, for U.S. government and contractor travel.

Location & Contact

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Physical address, phone number, and website for this facility. Use the directions link to get driving directions via Google Maps.
Address:
Aïn Oussera, Djelfa Province, Algeria
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Plant Facts

About This Site

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Written by NukeWorker from public records: facts that do not change. Operator, status and capacity come from the live data elsewhere on this page. Sources: Wikipedia: Es-Salam nuclear reactor; NEI Magazine: Algerian research reactor restarts after upgrades.

Es-Salam (El Salim) is a research reactor in Algeria in the Aïn Oussera area of Djelfa Province, near Birine, about 125 to 250 km south of Algiers depending on the source. It was Algeria's second research reactor.

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Algeria signed a nuclear cooperation agreement with China in 1983, and construction of the Chinese-supplied reactor began in 1988. It is a 15 MW thermal, heavy-water-moderated reactor fueled with low-enriched uranium, designed for radioisotope production, neutron activation analysis, neutron radiography and training. It first reached criticality on 17 February 1992, and an IAEA safeguards agreement for the reactor was concluded in 1992. Regular operation began in late 1993.