skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Method for automatically scramming a nuclear reactor

Abstract

An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.

Inventors:
; ;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1175596
Patent Number(s):
6,980,619
Application Number:
10/801,220
Assignee:
Battelle Energy Alliance, LLC (Idaho Falls, ID) INL
DOE Contract Number:
AC07-99ID13727
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Ougouag, Abderrafi M., Schultz, Richard R., and Terry, William K.. Method for automatically scramming a nuclear reactor. United States: N. p., 2005. Web.
Ougouag, Abderrafi M., Schultz, Richard R., & Terry, William K.. Method for automatically scramming a nuclear reactor. United States.
Ougouag, Abderrafi M., Schultz, Richard R., and Terry, William K.. Tue . "Method for automatically scramming a nuclear reactor". United States. doi:. https://www.osti.gov/servlets/purl/1175596.
@article{osti_1175596,
title = {Method for automatically scramming a nuclear reactor},
author = {Ougouag, Abderrafi M. and Schultz, Richard R. and Terry, William K.},
abstractNote = {An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 27 00:00:00 EST 2005},
month = {Tue Dec 27 00:00:00 EST 2005}
}

Patent:

Save / Share:
  • An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication withmore » the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.« less
  • The method described comprises the moving of a sufficiently sensitive detector, according to a program, on a path along which the radiation intensity has an exponential dependence of the space coordinate. The detector signal is compared with another fixed signal, and the output signal is fed from the comparator into the drive mechanism of the control elements which are then moved according to the value of that signal. When the chosen reactor power is reached, the movement of the detector is stopped. (Gmelin Institute)
  • Described is a method of automatically monitoring the power distribution of a nuclear reactor during normal power operation employing in-core detectors maintained within the thermal environment of the reactor at a prearranged storage location, normally outside the core reactivity region. The detectors are intermittently inserted into the core region according to a periodic predetermined time program. Upon insertion, the detectors are moved along corresponding preselected linear paths which terminate at the detector storage locations. Detector output vs. position is continuously recorded during travel to provide a partial core flux map. Four detectors, arranged in two electronically redundant groups, are alternatelymore » inserted into the core at staggered intervals dictated by the time program to obtain the desired flux information. Reinitiation of the program is effected upon a given movement of the reactor control rods to remap the corresponding reactivity changes and provide a complete and updated readout of the reactor core power distribution.« less
  • An apparatus is described for automatically starting up a nuclear reactor, which causes control rods in the reactor to be withdrawn in the predetermined order according to the signal obtained by adding the heat-up ratio as a compensatory component determined by the reactor pressure to the deviation of the heat-up ratio of the reactor temperature from the predetermined heat-up ratio and which causes the reactor to be subjected to heat-up and pressurization by opening turbine bypass valves when the heat-up ratio exceeds a reference value.