European Nuclear Society
e-news Issue 17 Summer 2007
http://www.euronuclear.org/e-news/e-news-17/nps-kth.htm

Unusual Concepts of Nuclear Power Reactors

NPS/KTH Seminar 2007-06-11
by Frigyes Reisch, frigyes@kth.se

SECURE and PIUS Innovative Power Reactor Designs with
Passive Safety Features

In Sweden an innovative reactor design was developed during the past decades. A reactor for district heating SECURE and a reactor for production of electricity PIUS (Process Inherent Ultimate Safety)
SECURE and PIUS are innovative light water cooled reactors with passive safety systems in a large pool of borated water in a concrete pressure vessel, located underground. The irradiated fuel can be stored inside the reactor cavity for thirty years. These features make the concept actual for today’s requirements.

An electrically heated test loop was built where the basic design characteristics were successfully verified. The concept was analyzed through detailed calculations with different computer codes.

Advances in Nuclear Science and Technology 1987

The Operating Principles of the PIUS Pimary System
Figure 1. The Operating Principles of the PIUS Pimary System

A.

A heat source (nulcear core) placed in a vertical pipe in a water pool will cause an upward flow in the pipe.

B.

If the heated water is returned to the lower end of the pipe there is no net flow from and to the pool.

C.

The heat generated can be extracted for a useful purpose. Mixing between hot circulated and cold pool water is prevented by stable stratification in tube bundles (density locks)

D.

By placing the pool in a closed vessel and pressuring with a steam bubble above the circulation system the latter can be operated at high pressure and temperature.

The operating principles of the SECURE primary system.
Figure. 2 The operating principles of the SECURE primary system.

Advances in Nuclear Science and Technology 1987

Heated Reactor Secure-H and Prestessed Concrete Vessel. Main Features of Nuclear Island.
Figure 3. Heated Reactor Secure-H and Prestessed Concrete Vessel. Main Features of Nuclear Island.

400 MWth, 2 MPa, exit temperature 190 0C

The ATLE test rig

The ATLE test rig

The Secure Heating Reactor

The ATLE test rig.
Figure 5. The ATLE test rig.

National Heat Conference
Portland, Oregon
August 5-9, 1995


Fig 6. Schematic of the PLUS Reactor. Same as Nuclear Safety article, Fig. 1, LA-UR-94-3467.

PIUS
Oak Ridge National Laboratory, September 1991

www.ornl.gov/info/reports/1991/3445603211254.pdf

September 1991

PIUS

www.analys.se/lankar/bkgr/bkgr1-99.pdf

ABB Atoms innovativa reaktorsystem, PIUS


© European Nuclear Society, 2007