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Title: TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR

Abstract

An analysis of the transient behavior of a 255-Mw(e) advanced sodium graphite reactor, previously described in NAA-SR-3829, is presented. The reactor and its components are briefly described. Nuclear and thermal characteristics are presented as far as they affect reactor kinetics or are essential in interpreting the results. The study includes an investigation of the inherent kinetic characteristics of the reactor, as well as and analysis of its transient behavior for all conceivable conditions of abnormal operations. Assumed reactor excursions are analyzed with and without ensuing protective system action. It is shown that the reactor is dynamically stable and that power transients which are followed by normal protective system actions will not lead to potentially unsafe conditions. The conclusion is reached furthermore, that uncontrolled rod withdrawal accidents from source power will be terminated by coolant choking'' and fuel meltdown before extensive coolant boiling occurs, and that the large thermal capacity and long-time constant of the upper plenum will provide protection against pool boiling for other less serious accidents until the reactor can be shut down by external means. (auth)

Authors:
Publication Date:
Research Org.:
Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
Sponsoring Org.:
USDOE
OSTI Identifier:
4823381
Report Number(s):
NAA-SR-3829(Suppl.1)
NSA Number:
NSA-16-004971
DOE Contract Number:
AT(11-1)-GEN-8
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ACCIDENTS; BOILING; CONTROL ELEMENTS; CONTROL SYSTEMS; COOLANT LOOPS; DELAYED NEUTRONS; EXCURSIONS; FAILURES; FUEL ELEMENTS; GRAPHITE MODERATOR; HEAT TRANSFER; HIGH TEMPERATURE; LIQUID METAL COOLANT; MELTING; NEUTRON FLUX; PLANNING; POWER PLANTS; PROMPT NEUTRONS; REACTIVITY; REACTOR CORE; REACTOR SAFETY; RODS; SHUTDOWN; SODIUM; SPECIFIC HEAT; STABILITY; TEMPERATURE; TRANSFER FUNCTIONS; TRANSIENTS

Citation Formats

Cappel, H.H.. TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR. United States: N. p., 1961. Web. doi:10.2172/4823381.
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Cappel, H.H.. TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR. United States. doi:10.2172/4823381.
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Cappel, H.H.. Fri . "TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR". United States. doi:10.2172/4823381. https://www.osti.gov/servlets/purl/4823381.
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@article{osti_4823381,
title = {TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR},
author = {Cappel, H.H.},
abstractNote = {An analysis of the transient behavior of a 255-Mw(e) advanced sodium graphite reactor, previously described in NAA-SR-3829, is presented. The reactor and its components are briefly described. Nuclear and thermal characteristics are presented as far as they affect reactor kinetics or are essential in interpreting the results. The study includes an investigation of the inherent kinetic characteristics of the reactor, as well as and analysis of its transient behavior for all conceivable conditions of abnormal operations. Assumed reactor excursions are analyzed with and without ensuing protective system action. It is shown that the reactor is dynamically stable and that power transients which are followed by normal protective system actions will not lead to potentially unsafe conditions. The conclusion is reached furthermore, that uncontrolled rod withdrawal accidents from source power will be terminated by coolant choking'' and fuel meltdown before extensive coolant boiling occurs, and that the large thermal capacity and long-time constant of the upper plenum will provide protection against pool boiling for other less serious accidents until the reactor can be shut down by external means. (auth)},
doi = {10.2172/4823381},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Dec 01 00:00:00 EST 1961},
month = {Fri Dec 01 00:00:00 EST 1961}
}
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Technical Report:
View Technical Report (2.80 MB)
DOI:  10.2172/4823381
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