Design and testing of the reactor-internal hydraulic control rod drive for the nuclear heating plant

Journal Article · Sun Nov 01 00:00:00 EST 1987 · Nucl. Technol.; (United States)

OSTI ID:5447442

Batheja, P; Meier, W J; Rau, P J

A hydraulically driven control rod is being developed at Kraftwerk Union for integration in the primary system of a small nuclear district heating reactor. An elaborate test program, under way for --3 yr, was initiated with a plexiglass rig to understand the basic principles. A design specification list was prepared, taking reactor boundary conditions and relevant German rules and regulations into account. Subsequently, an atmospheric loop for testing of components at 20 to 90/sup 0/C was erected. The objectives involved optimization of individual components such as a piston/cylinder drive unit, electromagnetic valves, and an ultrasonic position indication system as well as verification of computer codes. Based on the results obtained, full-scale components were designed and fabricated for a prototype test rig, which is currently in operation. Thus far, all atmospheric tests in this rig have been completed. Investigations under reactor temperature and pressure, followed by endurance tests, are under way. All tests to date have shown a reliable functioning of the hydraulic drive, including a novel ultrasonic position indication system.

• Research Organization: Kraftwerk Union AG, Hammerbacherstrasse 12 + 14, 8520 Erlangen (DE)
• OSTI ID: 5447442
• Journal Information: Nucl. Technol.; (United States), Vol. 79:2
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CONTROL ROD DRIVES
COMPUTERIZED CONTROL SYSTEMS
DESIGN
TESTING
HEAT DISTRIBUTION SYSTEMS
POWER REACTORS
COMPUTER CODES
DISTRICT HEATING
FEDERAL REPUBLIC OF GERMANY
HYDRAULICS
NUCLEAR POWER PLANTS
SCALE MODELS
SPECIFICATIONS
THERMODYNAMICS
CONTROL SYSTEMS
ENERGY SYSTEMS
EUROPE
FLUID MECHANICS
HEATING
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
REACTORS
STRUCTURAL MODELS
THERMAL POWER PLANTS
WESTERN EUROPE
220400* - Nuclear Reactor Technology- Control Systems
210600 - Power Reactors
Auxiliary
Mobile Package
& Transportable
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)