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

Abstract

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.

Authors:
; ;
Publication Date:
Research Org.:
Kraftwerk Union AG, Hammerbacherstrasse 12 + 14, 8520 Erlangen (DE)
OSTI Identifier:
5447442
Resource Type:
Journal Article
Journal Name:
Nucl. Technol.; (United States)
Additional Journal Information:
Journal Volume: 79:2
Country of Publication:
United States
Language:
English
Subject:
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)

Citation Formats

Batheja, P., Meier, W.J., and Rau, P.J. Design and testing of the reactor-internal hydraulic control rod drive for the nuclear heating plant. United States: N. p., 1987. Web.
Batheja, P., Meier, W.J., & Rau, P.J. Design and testing of the reactor-internal hydraulic control rod drive for the nuclear heating plant. United States.
Batheja, P., Meier, W.J., and Rau, P.J. Sun . "Design and testing of the reactor-internal hydraulic control rod drive for the nuclear heating plant". United States.
@article{osti_5447442,
title = {Design and testing of the reactor-internal hydraulic control rod drive for the nuclear heating plant},
author = {Batheja, P. and Meier, W.J. and Rau, P.J.},
abstractNote = {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.},
doi = {},
journal = {Nucl. Technol.; (United States)},
number = ,
volume = 79:2,
place = {United States},
year = {1987},
month = {11}
}