Fluid dynamical analysis for idealized reactors system with spherical symmetry determines the effect which the destructive component of a nuclear accident produces on primary containment structures. Steel strands surrounding the reactor cavity in the biological shield exhibit plastic deformation to achieve the energy absorption

Fistedis, S. H.

Sorensen, H. C.

English

NASA Technical Reports Server

February 1969
	
Brief 69-10046 
.
tjGY
AEC-NASA TECH BRIEF 
AEC-NASA Tech Briefs describe innovations resulting from the research and development program 
of the U.S. AEC or from AEC-NASA interagency efforts. They are issued to encourage commercial 
application. Tech Briefs are published by NASA and may be purchased, at 15 cents each, from 
the Clearinghouse for Federal Scientific and Technical Information, Springfield, Virginia 22151. 
Hydrodynamics of a New Concept of Primary Containment 
by Energy Absorption 
I Shield 
Inert Gas
To determine the effect the destructive component 
of a nuclear accident produces on a primary contain-
ment structure, a fluid dynamical analysis has been 
made for an idealized reactor system having spherical 
symmetry. 
To reduce the cost of primary nuclear containment 
and to provide reliable safety factors for credible 
nuclear accidents, a new approach for primary con-
tainment by energy absorption is proposed. High-
strength steel strands are placed in the biological 
shield to form a basketlike configuration around 
the reactor cavity. The strands are placed in conduits 
to prevent bond with the concrete. The energy-absorb-
ing process is accomplished by the plastic deformation 
that the strands are capable of exhibiting. This ap-
proach eliminates the expensive multiple steel cylin-
ders in the reactor cavity and extends the primary 
containment system to include the concrete biological 
shield.
Inert Gds
	
Reirtor Vessel 
The purpose of the investigation is to make a fluid 
dynamical analysis of the energy release of a nuclear 
accident in order to (I) obtain general information on 
how the destructive component propagates and 
changes with time, and (2) determine the effect of the 
destructive component on the concrete primary -con-
tainment structure so that the rate of strain for the 
strands can be calculated. The destructive component 
is separated into three elements: (I) The shock wave: 
(2) The fluid momentum due to passage of the shock 
wave: and (3) The expanding gas bubble at high tem-
perature and pressure pushing on the fluid. 
Two solutions for an example problem are given. 
Part I presents the solution for an ideal reactor sys-
tem (left figure) that does not include the reactor 
vessel. Part II gives the solution for the same ideal 
reactor system but with the reactor vessel included 
(right figure). In each case, the effect the destructive 
component produces on the concrete containment 
This document was prepared under the sponsorship of the Atomic 
Energy Commission and/or the National Aeronautics and Space 
Administration. Neither the United States Government nor any per-
son acting on behalf of the United States Government assumes any
liability resulting from the use of the information contained in this 
document, or warrants that the use of any information, apparatus, 
method, or process disclosed in this document may not infringe pri-
vately owned rights. 
https://ntrs.nasa.gov/search.jsp?R=19690000046 2020-03-16T17:50:20+00:00Z
structure is determined from computer results and is 
discussed. The results of the two solutions are then 
compared. 
The partial differential equations describing the 
fluid motion of the destructive component are based 
upon the von Neuman n—Richtmeyer artificial-viscos-
ity technique and are presented in Lagrangean form. A 
numerical solution, based upon finite-difference ap-
proximations of these equations is obtained by the use 
of a CDC-3600 digital computer. 
Notes 
I. This information, conducted by H. C. Sorensen 
and S. H. Fistedis of Argonne National Labora-
tory, has been reported in "Hydrodynamics of a 
New Concept of Primary Containment by Energy 
Absorption, " ANL-7214, December 1966. This re-
port is available from the Clearinghouse for Federal 
Scientific and Technical Information, Springfield, 
Virginia 22151; Price - $3.00 each (microfiche 
$0.65). 
2. The report includes details of the computer analy-
sis and a complete discussion of the results. 
3. This information would be helpful in studies of 
explosion containment by reinforced-concrete ex-
plosive storage or processing structures. 
4. The work could prove helpful in the analysis and 
design of curtain walls and protective structures 
for the chemical and petrochemical industries. 
Vessels for high temperature and pressure proces-
ses and their protective structre could at least be 
qualitatively treated since the code uses chemical 
rather than nuclear explosives.
Inquiries concerning this report may be directed to:

Office of Industrial Cooperation 
Argonne National Laboratory 
9700 South Cass Avenue 
Argonne, Illinois 60439 
Reference: B69-10046 
Source: H. C. Sorensen and S. H. Fistedis

Reactor Engineering Division

of Argonne National Laboratory

(ARG-10242) 
Patent status: 
Inquiries about obtaining rights for commercial use 
of this innovation may be made to: 
Mr. George H. Lee, Chief 
Chicago Patent Group 
U.S. Atomic Energy Commission 
Chicago Operations Office 
9800 South Cass Avenue 
Argonne, Illinois 60439 
Brief 69-10046	 Category 05


Hydrodynamics of a new concept of primary containment by energy absorption

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