Published April 2013 | Version v1
Report

New Irradiation Device at the Budapest Research Reactor

  • 1. Hungarian Academy of Sciences KFKI Atomic Energy Research Institute Budapest (Hungary)

Description

In close cooperation with the Paul Scherer Institute (Switzerland) two new rigs called BAGIRA (Budapest Advanced Gas cooled Irradiation Rig with aluminium structure) have been built. The irradiation volume of the largest rig is 360 x 20 x 30 mm and it can operate in the temperature range of 150-650oC. The heating is combined gamma and electrical heating; the temperature measurement is performed by 6 thermocouples, and controlled by a helium-nitrogen gas mix flow. The neutron flux within the rig is about 2-6 x 1013 n.cm-2s-1. Similar but smaller irradiation channel have been built for long term irradiations at lower temperature for testing the materials of the fusion reactor. Altogether 24 different irradiations have been performed until now studying the radiation resistance of RPV steels, model alloys, titanium and tungsten, aluminium alloys and ceramics. In 2010 the irradiation facilities of the BRR were under upgrade again. The purpose of the modernisation was to satisfy the requirements at the development and testing of materials for the third and fourth generation reactors, fusion devices and advanced testing of presently used materials. The new irradiation rig is: i) Shielded from the thermal neutrons by boron carbide shield (better fast/thermal neutron ratio, less gamma heat generation, less activation of the samples); ii) The temperature range of the operation is increased up to 600oC; iii) The minimum stable operation temperature is as low as 100oC; iv) The target can be rotated during irradiation to avoid self-shield; v) The temperature control became to electric resistance heating in 6 zones instead of the present 3 zones; vi) The sample removal after irradiation simplified and the personal dose during sample removal will be reduced; vii) The mass of the activated structure also reduced and also the preparation costs of a new irradiation reduced; viii) Further new feature of the design is the in-pile creep and low cycle fatigue test on small size specimens. (author)

Part of:
Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

Additional details

Identifiers

Publishing Information

ISBN
978-92-0-191210-7
Imprint Title
Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
p. 315-321
ISSN
1684-2073
Report number
IAEA-TECDOC-CD--1693

Conference

Title
IAEA-HOTLAB Technical Meeting on Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel
Dates
23-27 May 2011
Place
Smolenice (Slovakia)

Optional Information

Notes
Figs., 10 refs.