No abstract available

[en] This paper describes the thermal power calibration and neutron flux measurement performed in order to have an approach to the IAN-R1 reactor core characterization in the framework of the recently acquired operating license for five years. (author)

[en] The associated Instrumentation & Control of the Research Nuclear Reactor IAN-R1, located in Colombia, was updated on the year 2012, as a direct result of the initiative by the Colombian Government represented by the Colombian Geological Survey (Servicio Geológico Colombiano). The result of the conversion from Highly-enriched MTR Nuclear fuel into Low-enrichment TRIGA Nuclear fuel guarantees a nuclear reactor that can be operated for several years. The present document presents the Current Technical Status (status of available infrastructure and utilization capabilities, including staff) of the reactor, its success stories, major achievements, and future prospects. (author)

[en] The IAN-R1 research reactor has undergone continuous substantial changes involving modifications to the instrumentation, power and fuel. The reactor group of the Institute of Nuclear Science and Alternative Energy (INEA) of the Ministry of Mines and Energy has endeavoured to improve the physical security of the reactor installations. Colombia has undertaken to maintain adequate physical protection measures with respect to the installations and the materials supplied, as well as any special fissionable material used, including subsequent generations of fissionable material produced. The paper gives details of the level of physical protection and the implementation of physical protection measures and the IAN-R1 research reactor and of the new project currently being developed under which the present system of security installed in the reactor will be upgraded and greater security will be applied to other sensitive installations of INEA. (author)

[en] With cooperation of the International Atomic Energy Agency (IAEA), neutronic calculations were carried out for conversion of the Ian-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. In order to establish a staff for neutronic calculation at the Instituto de Cancan's Nucleares y Energia s Alternatives (INEA) a program was established. This program included training, acquisition of hardware, software and calculation for the core with MTR-HEU fuel , enriched nominally to 93% and calculation for several arrangements with the TRIGA-LEU fuel, enriched to 19.7%. The results were verified and compared with several groups of calculation at the Instituto Nacional de Investigaciones Nucleares (ININ) in Mexico, and General Atomics (GA) in United States. As a result of this program, several technical reports have been wrote. (author)

[en] The Institute of Nuclear Sciences and Alternative Energies (INEA) in Bogota, Colombia, has operated since 1965, a small 10 kW(t) research reactor, known as the IAN-R1 reactor, which was upgraded to 30 kW(t) in 1980. This reactor was provided to the Republic of Colombia under the U.S. Atoms for Peace Program, and which has been fueled with MTR HEU fuel, enriched nominally to 93% U-235. With the cooperation of the International Atomic Energy Agency (IAEA), a gradual reactor upgrade program has been undertaken beginning in 1987. The first step in this program was the upgrade of reactor instrumentation and control systems. In December, 1994, the IAEA and INEA entered into a tripartite contract with General Atomics (GA) to prepare a new safety analysis report for performing an HEU to LEU conversion of the R-1 reactor, manufacture TRIGA type LEU (19.7% enriched) fuel to replace the original MTR-HEU fuel plate assemblies, upgrade the reactor power to 100 kW(t), carry out additional upgrades of auxiliary reactor systems and commission the reactor with TRIGA fuel. (author)

No abstract available