Published March 1990 | Version v1
Report Open

Improvement of pulsing operation performance in the Nuclear Safety Research Reactor (NSRR)

  • 1. Japan Atomic Energy Research Inst., Tokyo (Japan)

Description

The Nuclear Safety Research Reactor (NSRR) is one of the TRIGA-type research reactors widely used in the world, and has mainly been used for studying reactor fuel behaviour during postulated reactivity-initiated accidents (RIAs). Its limited pulsing operation capability, however, could produce only a power burst from low power level simulating an RIA event from essentially zero power level. A computerized automatic reactor control system was developed and installed in the NSRR to simulate a wide range of abnormal events in nuclear power plants. This digitalized reactor control system requires no manipulation of the control rods by reactor operators during the course of the pulsing operation. Using this fully automated operation system, a variety of power transients such as power ramping, power bursts from high power level, and so on were made possible with excellent stability and safety. The present modification work in the NSRR and its fruitful results indicate new possibilities in the utilization of the TRIGA type research reactor

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Part of:
Proceedings of the international symposium on research reactor safety operations and modifications

Additional details

Publishing Information

Imprint Title
Proceedings of the international symposium on research reactor safety operations and modifications
Imprint Pagination
610 p.
Journal Page Range
p. 986-993.
Report number
AECL--9926(v.3)

Conference

Title
International symposium on research reactor safety operations and modifications.
Dates
23-27 Oct 1989.
Place
Chalk River, ON (Canada).

Optional Information

Secondary number(s)
IAEA-SM--310/5P.