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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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).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22047714
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MODIFICATIONS; NSRR REACTOR; ON-LINE CONTROL SYSTEMS; PERFORMANCE; REACTOR CONTROL SYSTEMS; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; ON-LINE SYSTEMS; OPERATION; PULSED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--310/5P.