U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 1-16
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The point of greatest concern, however, involves "conceivable," i.e.,
incredible but imaginable, accidents that could render ineffective the
containment vessel or, for that matter, any other engineered safety fea-
tures. Present technology is adequate to provide containment or safety
features or both for nuclear facilities that would permit their location
in population centers and still meet the existing requirements for ex-
clusion area and low-population zone. This possibility is precluded,
however, in the present site criteria by the specified population-center
distance. As experience is acquired and safety analyses become more
sophisticated, it may be anticipated that the present site criteria, which
are based on distance, will give way to criteria that will be based on
total population exposure. Such site criteria might, for example, still
employ the exclusion-area concept as a means for limiting the maximum ex-
posure to any one off-site individual, and the low-population zone and
population-center distances might evolve into a total-population-exposure
requirement. The AEC encourages applicants "to demonstrate to the Com-
mission the applicability and significance of considerations other than
those set forth in the guides" in order to take into consideration addi-
tional containment and engineering safeguards that may reduce the exclu-
sion area, low-population zone, and population center distances.
It may be many years, however, before sufficient experience has been
developed to permit a major reorientation of siting policy. In the mean-
time the existing site criteria provide a workable and generally consis-
tent basis for siting reactors.
1.2.2 Nuclear Merchant Ship Site Criteria
The safeguards review of the N.S. Savannah by the Advisory Committee
on Reactor Safeguards (ACRS) and the Division of Licensing and Regulation
was concluded during the summer of 1962 with authorization, on August 3,
for interim operation extending over a six-month period and covering
approximately six port areas. As a consequence of the study that led to
this authorization, the Maritime Administration-AEC Joint Group developed
a guide for the "Port Operation of Shipboard Reactors. "t18 The principal
part of this guide modified the AEC Reactor Site Criterial in such a man-
ner as to make some allowance for the mobility of the ship reactor and to
arrive at criteria that would be compatible with both the inherent aspects
of nuclear merchant vessels and the safety philosophy expressed in the
existing site criteria.
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Cottrell, William B. & Savolainen, A. W. U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1, report, August 1965; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101033/m1/44/: accessed March 18, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.