U.S. patent number 3,871,842 [Application Number 05/269,272] was granted by the patent office on 1975-03-18 for exhaust gas cleaning system for handling radioactive fission and activation gases.
This patent grant is currently assigned to Licentia-Patent-Verwaltungs G.m.b.H.. Invention is credited to Horst Queiser, Horst Schwarz.
United States Patent |
3,871,842 |
Queiser , et al. |
March 18, 1975 |
EXHAUST GAS CLEANING SYSTEM FOR HANDLING RADIOACTIVE FISSION AND
ACTIVATION GASES
Abstract
An exhaust gas cleaning system utilizing the principle of
delaying radioactive gases to permit their radioactive decay to a
level acceptable for release to the atmosphere, comprising an
adsorbent for adsorbing radioactive gas and a container for
containing the adsorbent and for constraining gas to flow through
the adsorbent, the adsorbent and the container forming
simultaneously an adsorptive delay section and a mechanical delay
section, by means of a predetermined ratio of volume of voids in
the adsorbent to total volume of the container containing the
adsorbent, for delaying radioactive gas to permit its radioactive
decay to a level acceptable for release to the atmosphere. A method
of using an adsorbent for cleaning a radioactive gas containing an
isotope which is adsorbed by the adsorbent and containing an
isotope whose adsorption by the adsorbent is low as compared to the
isotope which is adsorbed and which is short-lived as compared to
the isotope which is adsorbed, comprising constraining the gas to
flow through the adsorbent with the retention time for the isotope
which is adsorbed being at least the minimum for permitting
radioactive decay to a level acceptable for release to the
atmosphere and with the retention time for the isotope of
relatively low adsorption and relatively short life being at least
the minimum for permitting radioactive decay to a level acceptable
for release to the atmosphere.
Inventors: |
Queiser; Horst (Hochstadt,
DT), Schwarz; Horst (Wiesbaden, DT) |
Assignee: |
Licentia-Patent-Verwaltungs
G.m.b.H. (Frankfurt, DT)
|
Family
ID: |
25761366 |
Appl.
No.: |
05/269,272 |
Filed: |
July 5, 1972 |
Foreign Application Priority Data
|
|
|
|
|
Jul 5, 1971 [DT] |
|
|
2133250 |
Jul 5, 1971 [DT] |
|
|
7125651 |
|
Current U.S.
Class: |
96/131; 376/314;
976/DIG.267; 976/DIG.378 |
Current CPC
Class: |
B01D
53/0423 (20130101); B01D 53/0446 (20130101); G21C
19/303 (20130101); G21F 9/02 (20130101); B01D
2253/102 (20130101); B01D 2257/93 (20130101); Y02E
30/30 (20130101); B01D 2257/11 (20130101) |
Current International
Class: |
B01D
53/06 (20060101); G21F 9/00 (20060101); G21C
19/303 (20060101); G21C 19/28 (20060101); G21F
9/02 (20060101); B01d 053/04 () |
Field of
Search: |
;55/66,74,387,179,58
;176/19,37 |
References Cited
[Referenced By]
U.S. Patent Documents
Primary Examiner: Hart; Charles N.
Attorney, Agent or Firm: Spencer & Kaye
Claims
It is claimed:
1. Apparatus for processing radioactive exhaust gases including
fission gases and activation gases, said apparatus comprising
preliminary adsorber means including a container, main adsorber
means including a container, and adsorber material filling each of
said adsorber containers, said main and preliminary adsorber means
being connected to form a series delay path between a source of
such exhaust gases and an exhaust gas chimney to constrain such
exhaust gases to flow through said absorber material and to be
delayed by said delay path in order to undergo radioactive decay,
said delay path providing essentially the only gas delay between
the source and the chimney, said preliminary adsorber means serving
to permit radioactive decay of those exhaust gas components which
constitute short-lived fission products and to filter out the
resulting daughter products, said preliminary adsorber means being
provided with shielding means and comprising means permitting easy
replacement of said adsorber material.
2. A system as claimed in claim 1 wherein said main adsorber means
include at least one concentrically arranged tube means for
dividing the interior of said main adsorber means container into a
plurality of space means for receiving said adsorber material, and
means for causing radioactive gas to flow through said space means
one after the other.
3. Apparatus as defined in claim 2, wherein there are a plurality
of centrally disposed pipes arranged concentrically.
4. Apparatus as defined in claim 1 wherein said container of said
preliminary adsorber means is composed of a cylindrical upper part
and a conical lower part, said replacement permitting means include
a discharge opening in said lower portion for the easy and safe
discharge of adsorber material, and said preliminary adsorber means
further comprise a gas inlet pipe extending into the interior of
said conical lower part for introducing radioactive exhaust gas
into said adsorber material.
5. A system as claimed in claim 4 wherein said preliminary adsorber
means further include an upper shielding floor means above said
upper part for shielding radiation emitted in said upper and lower
parts, and a lower shielding floor means below said lower part for
shielding radiation emitted in said upper and lower parts, and said
replacement permitting means further include pipe means for
delivering adsorber material down through said upper floor means
and into said upper and lower parts, and a discharge tube means for
extracting adsorber material from said discharge opening down
through said lower floor means.
6. Apparatus as defined in claim 5 further comprising a vacuum
chamber in which said main adsorber means is situated, and means
connected for controlling the temperature of said chamber.
7. Apparatus as defined in claim 1 for processing exhaust gases
whose fission gases include krypton and xenon and whose activation
gases include nitrogen isotopes and oxygen isotopes.
8. Apparatus as defined in claim 1 wherein said main adsorber means
filled with adsorber material forms simultaneously an adsorptive
and a mechanical delay path by a predetermined ratio of the void
volume in said adsorber material to the volume of said container
for said adsorber material.
9. An exhaust gas cleaning system utilizing the principle of
delaying radioactive gases to permit their radioactive decay to a
level acceptable for release to the atmosphere, comprising
adsorbent means for adsorbing radioactive gas, said adsorbent means
being divided into two portions, a preliminary adsorber containing
one of said portions, for delaying radioactive gas and for
filtering out solid daughter products, and a main adsorber
containing the other of said portions, for further delaying
radioactive gas which has passed through said preliminary adsorber
means and for further filtering out of solid daughter products,
said preliminary adsorber including a cylindrical upper part, a
coaxial conical lower part connected to and tapering narrower
downwardly from the cylindrical upper part, said conical part
having means for adsorbent removal, and a pipe opening into the
interior of said conical lower part for the introduction of
radioactive gas into said adsorbent means, an upper shielding floor
above said upper part for shielding radiation emitted in said upper
and lower parts, a lower shielding floor below said lower part for
shielding radiation emitted in said upper and lower parts, means
for filling the portion of said adsorbent means associated with
said preliminary adsorber extending downwardly through said upper
floor into said upper and lower parts, and a discharge means
extending downwardly from said extraction opening means through
said lower floor.
Description
BACKGROUND OF THE INVENTION
The present invention relates to an apparatus for cleaning
radioactive gases to permit safe disposal into the atmosphere.
The radioactive fission and activation gases set free in nuclear
reactors must be treated before their release to the atmosphere.
The purpose of this treatment is to prevent there occurring an
unacceptably high contamination of the environmental air around the
nuclear reactors, with the unacceptable radiation load associated
with such contamination.
In the treating of such exhaust gases, it is primarily a matter of
delaying them to permit their radioactive decay to satisfactory
levels. The article, "Reactorabgas und Gebaudeabluftbehandlung im
Kernkraftwerk mit Siedewasserreactor (in translation, Reactor
Exhaust Gas and Building Exhaust Air Treatment in the Nuclear Power
Plant with Boiling Water Reactor)", published in the August 1970,
(Volume 16, No. 8) issue of Atom und Strom (in translation, Atom
and current), pages 115 to 118, shows a treatment system wherein
the gas is first mechanically delayed in a long pipeline circuit,
so that short-lived active substances, primarily nitrogen and
oxygen isotopes, can decay. That this mechanical delaying is needed
has been clear for the known treatment plants, because nitrogen and
oxygen can only be delayed adsorptively to a limited extent.
The article gives an introduction to the basics of exhaust gases
containing radioactive components. In the case of a boiling water
reactor, the gases which arise by activation are primarily isotopes
of oxygen, nitrogen, and argon.
Following the mechanical delay section of the treatment system of
the article comes a mechanical filter, whose purpose is to collect
the solid daughter products arising during the decay of the active
gases in the mechanical delay section. Then following the filter
comes a purely adsorptive delay section, where the longer-lived
radioactive substances are caught on the surface of the adsorbent
by free surface forces and consequently delayed. Of concern here
are primarily only the noble gases xenon and krypton. The solid
fission products resulting in the adsorptive delay section can be
active; they are separated at the end of the adsorptive delay
section by a mechanical filter. Since the adsorptive delaying
action increases with decreasing moisture in the mixture to be
delayed, the described system provides a gas drying step before the
adsorptive delay section.
The described method has the disadvantage of necssitating a large
expense for apparatus, in order to achieve exhaust gas cleaning.
This is especially true in the case of the mechanical delay
section, which is formed by a long pipeline circuit. Since
condensate inherently forms in the pipeline circuit, a complex
dewatering system is necessary. In the case of operation at
pressures below atmospheric, the problems of condensate removal
become greater.
The mechanical delay section is also caused to be large because of
the parabolic flow distribution in the pipelines. The flow velocity
is thus higher in the center of a pipe than at the wall. This means
that the retention time for material to be delayed can take on
different values. However, the designing of the delay section has
to be carried out on the basis of the flow velocity at the center
of the pipes.
The large volumes associated with this prior system requires
expensive radiation shielding, both for the pipeline circuit and
for the space where the removed condensate is collected.
SUMMARY OF THE INVENTION
An object of the present invention, therefore, is to provide an
exhaust gas cleaning system for decreasing the apparatus expense as
compared to the above-described system; at the same time, cleaning
ability is not to be negatively influenced.
A further object is to avoid problems of condensate removal for the
mechanical delay section, to hold the volume of the mechanical
delay section as small as possible, and, as a result of such small
volume, to hold radiation shielding expenses small.
These as well as other objects which will become apparent in the
discussion that follows are achieved, according to the present
invention, by:
1. an exhaust gas cleaning system utilizing the principle of
delaying radioactive gases to permit their radioactive decay to a
level acceptable for release to the atmosphere, comprising
adsorbent means for adsorbing radioactive gas and container means
for containing the adsorbent means and for constraining gas to flow
through the adsorbent means, the adsorbent means and the container
means forming simultaneously and adsorptive delay section and a
mechanical delay section, by means of a predetermined ratio of
volume of voids in the adsorbent means to total volume of the
container means containing adsorbent means, for delaying
radioactive gas to permit its radioactive decay to a level
acceptable for release to the atmosphere; and
2. a method of using an adsorbent for cleaning a radioactive gas
containing an isotope which is adsorbed by the adsorbent and
containing an isotope whose adsorption by the adsorbent is low as
compared to the isotope which is adsorbed and which is short-lived
as compared to the isotope which is adsorbed, comprising
constraining the gas to flow through said adsorbent with the
retention time for the isotope which is adsorbed being at least the
minimum for permitting radioactive decay to a level acceptable for
release to the atmosphere and with the retention time for the
isotope of relatively low adsorption and relatively short life
being at least the minimum for permitting radioactive decay to a
level acceptable for release to the atmosphere.
GENERAL ASPECTS OF THE INVENTION
The objects of the invention are achieved in an exhaust gas
cleaning system with a mechanical and an adsorptive delay section
for treating radioactive fission and activation gases, wherein the
adsorptive delay section simultaneously forms the mechanical delay
section for the gas mixture to be treated, this being accomplished
by appropriately choosing the ratio of the volume of voids between
the particles of the adsorbent making up the adsorptive delay
section to the total volume into which adsorbent is filled.
BRIEF DESCRIPTION OF THE DRAWINGS
FIG. 1 is a schematic flow diagram of an exhaust gas treatment
plant according to the invention.
FIG. 2 is a partially schematic elevational view of a main adsorber
of the present invention.
FIG. 3 is a partially schematic elevational view of a preliminary
adsorber of the invention.
FIG. 4 is a partially schematic plan view of a plant according to
the invention in a vacuum chamber.
DESCRIPTION OF THE PREFERRED EMBODIMENTS
As brought out in the BACKGROUND OF THE INVENTION, radioactive gas
to be cleaned according to the invention can contain nitrogen and
oxygen as isotopes which are relatively unadsorbed and of low
half-life, while containing xenon and krypton and isotopes of
relatively greater half-life which are adsorbed.
It is preferred to provide the system of the present invention with
a preliminary adsorber, with the gas mixture to be treated being
first delayed adsorptively there and then being filtered for
removal of solid daughter products resulting from active gas decay.
Then, in a main adsorber, the remaining, longer-lived isotopes are
delayed adsorptively and mechanically, with the resulting solid
daughter products being again filtered off.
An example of the invention will now be described with reference to
the drawings, firstly with reference to FIG. 1. The radioactive
fission and activation gas to be treated is sucked out of a turbine
condenser (not illustrated) by evacuation pump 1 and, in mixture
with the driving steam, fed to the exhaust gas treating plant.
After a slight superheating of the steam/gas mixture in a heater 2,
the mixture moves on to recombiner 3, where free hydrogen and
oxygen in the mixture are burned to water on the surface of a
catalyst, for example of platinum. The heat given off by the
exothermic reaction causes a large temperature increase.
Temperatures of 400.degree.C in the mixture are comprehended. The
thus strongly superheated steam/gas mixture goes next into a
condenser 4 and then a cooler 5. The driving steam and the steam
from the radiolysis gas being burned to water are largely condensed
and withdrawn, so that only an inert gas mixture, composed
primarily of air with some remaining steam, comes from cooler
5.
The flow diagram shows a second, parallel line of devices 1 to 5.
Such technique is used, for example, in the system described in the
article mentioned above.
Following the condenser 4 and cooler 5 is a gas cooling and drying
plant 6. The gas leaving the cooler and dryer 6, usually will be at
a temperature in the range of 0.degree.-30.degree.C, with a
humidity corresponding to a dew point in that range. Then comes
preliminary adsorber 7, and a second preliminary adsorber 7', which
is used as needed. Following directly on preliminary adsorber 7 is
the main adsorber 8. The main adsorber can include one or more
adsorption columns. There follows vacuum pumps 9 and 9', by which
the treated gas is led to an exhaust air and exhaust gas chimney
10.
The essential components of the exhaust gas cleaning system are the
preliminary adsorber 7, and perhaps 7', and the main adsorber 8.
The preliminary adsorber, which usually represents the smaller part
of the adsorption plant, serves essentially for the decay of the
short-lived fission products, present as the vastly greater portion
of the gaseous nuclide mixture. In conformance with the high
proportion at which the short-lived fission products are present,
there is a correspondingly large heat and daughter product
production. The forming solid daughter products are simultaneously
filtered off. The preliminary adsorber is constructed in such a
manner that the adsorbent, and the solid daughter products, which
deposit in the adsorbent and are thus filtered off simultaneously,
can be exchanged easily and without danger. Further details will
become apparent with the description of FIG. 3 below.
The main adsorber, which usually represents the larger part of the
system, serves both for mechanically and adsorptively delaying the
remaining, longer-lived isotopes and for the filtering of the
resulting solid daughter products. The container of the main
adsorber 8 is, therefore, of larger volume than the preliminary
adsorber and is provided with simple installations for an
improbable, yet conceivable, exchange of the adsorbent.
By choosing a suitable ratio of volume of voids in the adsorbent to
the total volume of container containing adsorbent, which ratio may
be controlled for example by the particular shape or size of
adsorbent particles used, it is possible to provide in main
adsorber 8 for the further decay of poorly adsorbable gas
components in the voids between the adsorbent packing bodies.
The main adsorber 8 can be provided in the form of a cylindrical
vessel having a floor on which the adsorbent lies. Gas flow-through
can be either from below upwards, or from above downwards. An
especially advantageous embodiment of the main adsorber is
illustrated in FIG. 2. A central tube 12 is arranged in standing
container 11; tube 12 divides the container 11 into two spaces 13
and 13' for receiving adsorbent 50, for example activated carbon.
These spaces are flowed through, one after the other. Depending on
particular circumstances, more central tubes 12 of other diameters
can be arranged concentrically in the standing container 11, so
that a larger number of separate spaces is provided for receiving
adsorbent. The locations of gas entrance and exit connections, and
filling and emptying connections for adsorbent, can be seen
likewise in FIG. 2.
In order to catch solid particles which might be carried out of the
main adsorber, no additional filter is needed. Rather, this
catching is done by using liquid-piston type rotary blowers to
forward the gas. The liquid needed for blower operation then
catches any low-activity solid impurities present in the gas. The
separation of the largely decayed and cleaned gas from the liquid
proceeds in a gas-water separator. A suitable liquid-piston type
rotary blower is shown in FIGS. 6 -47 on page 6-24 of PERRY'S
CHEMICAL ENGINEER'S HANDBOOK, McGraw-Hill, New York, 1963.
A preferred embodiment of the preliminary adsorber 7 (or 7') is
shown in FIG. 3. Included are a cylindrical upper part 14 and a
conical lower part 15. Pipe 16 extends from above down into the
interior of the chamber formed by parts 14 and 15; gas enters from
this pipe into adsorbent 51, for example activated carbon. Lid 20
closes the top of the chamber. A gas distributor 17 on the end of
pipe 16 provides for the emission of the gas into the adsorbent
while at the same time preventing an encroachment of the adsorbent
from the area between the outside of pipe 16 and the inner walls of
parts 14 and 15, into pipe 16. For reasons of radioactivity and
easy filling and emptying, the preliminary adsorber 7 is arranged
between an upper shielding floor 18 and a lower shielding floor 19.
A filling pipe 21, for the filling of packing bodies carrying
adsorbent, is accessible from above the upper shielding floor 18
and opens into the adsorbent chamber through lid 20. For the
emptying of adsorbent, a discharge tube 22 extends downwardly from
the lower end of conical part 15, through lower shielding floor 19,
into the space beneath. Either a part, or all, of the adsorbent can
be extracted from the adsorbent chamber through tube 22 and into
one or more transport vessels. Control of the adsorbent emptying is
accomplished by a push gate 23 in the discharge tube 22. Because
the pipe 16 extends down into the conical lower part 15, it is
possible to empty first always the most strongly loaded adsorbent
through discharge tube 22. Thus, that portion of the adsorbent in
the vicinity of the gas distributor 17 provides the greatest
filtering and retention of solid daughter products. Fresh adsorbent
can then be added for make-up purposes through filling pipe 21.
A transport car 24 with vessel 25 can serve for receiving and
carrying away the emptied adsorbent. Sealing between the vessel 25
and discharge tube 22 is done using a plastic sack according to
conventional welding techniques.
As indicated by the arrows in FIGS. 3 and 2, a radioactive gas to
be cleaned first flows from the cooling and drying plant 6 in FIG.
1 into pipe 16 in FIG. 3, out into the adsorbent 51, upwards in
part 14, and out through pipe 52 in lid 20. Pipe 52 is connected to
pipe 53 in FIG. 2. Gas flowing into pipe 53 flows upwards through
space 13' and then turns down through the outer, annular space 13,
finally to leave, in cleaned state, through pipe 54. Adsorbent is
filled into space 13' through connection 55a; into space 13 through
connection 55b. Adsorbent may be removed from space 13 through
connection 56b and from space 13' through connection 56a.
The method of the present invention provides longer delay times if
pressures above atmospheric are used and also if cooling is
provided. But then, the use of a below-atmospheric pressure chamber
can improve the exhaust gas cleaning system still further. Such is
illustrated in FIG. 4. Thus, usually, radioactive exhaust gas
cleaning systems are operated at pressures below atmospheric for
reasons of safety.
The below-atmospheric or vacuum chamber includes a concrete housing
30 for the purpose of providing shielding from radiation. The inner
walls of this housing are lined with a heat insulation 31. The
vacuum chamber surrounds the main adsorber 8, which in this
embodiment includes three adsorption chambers 32, 32', and 32". The
vacuum chamber is accessible through an air lock 33, which is
closed during normal operation. Ventilation of the vacuum chamber
is done using an air introduction line 34 and an air extraction
line 35.
The air sucked out of the vacuum chamber, as well as the air which
is introduced, is passed through an ultrafine filter 36 and an
activated carbon filter 37 by means of a blower 38, whose suction
side faces filter 37, in conformance with the arrows indicating air
flow in the vacuum chamber. On the pressure side of blower 38,
throttle valves 39 and 40 are adjusted with respect to one another
to recycle a portion of the air while sending the remainder to the
chimney 42. The air recycled to the vacuum chamber can be sent
through a cooler 41, as shown, with the gas in line 34 being in the
range -20.degree.C to +20.degree.C. The throttle valve 57 controls
the admission of fresh air to the system.
FIG. 4 further shows that the gas mixture to be treated in the main
adsorber 8 is first passed through a compressor 43, whose pressure
side faces chamber 32 in the drawing. Upon leaving the main
absorber, the gas moves through an expansion valve 44 and thence
out of the vacuum chamber and into chimney 42. In this system the
pressure within chamber 30 is in the range 0.95-1 atm. and the
pressure downstream of compressor 43 is in the range 0.8-20
atm.
A significant advantage of the exhaust gas cleaning system of the
present invention resides in its elimination of a separate
mechanical delay section, so that the total system becomes cheaper
and less demanding of space. Since the mechanical delay takes place
after the cooling, condensing, and drying provided by apparatus
components 4, 5, and 6 described above, condensate does not occur
during the mechanical delay. By filling the adsorbers with
adsorbent, a substantially constant gas flow velocity is obtained
across the adsorber cross sections; this enables an excellent
utilization of the volume available for mechanical delay.
The space saving aspect of the present invention means that lesser
amounts of radiation shielding are needed.
Because the preliminary adsorber is arranged between two shielding
floors, it is possible to fill and empty adsorbent with safety.
The dividing of the main adsorber up into a plurality of concentric
adsorbent-receiving chambers also saves space, as compared with a
practice of providing the adsorbent in a plurality of separate
columns.
The preferred activated carbon, which is used as adsorbent, has the
following specification:
particle size 1-3 mm internal surface 1000 m.sup.2 /g bulk density
0.5 g/m.sup.3
This carbon is manufactured by Bergwerksverband, Essen-Kray,
Frillendorferstra.beta.e 351. The trademark name is "Aktivkohle Typ
VRG 1-3".
The release rates at the stack are based on the permissible
exposure rates at the location of the power plant. The permissible
rates both in the United States of America and in Germany are in
the range of 5-50 mrm/a (millirem per annum). This means-depending
on the meteorological conditions at the site-values at the
stack-outlet of the power plant in the range of 1-100 Curie/h (see
the article, mentioned on page 3, lines 13 to 19.)
To design the exhaust gas cleaning system for handling the
radioactive fission and activation gases there must be known the
kind, the quantity and the activity of the radioactive gases to be
treated in connection with the maximum radiation level in gases to
be released to the atmosphere as mentioned above.
Examples of the kind, the quantity and the activity of the
radioactive gases in connection with a boiling water reactor are
given in the above-mentioned article and also in the article: "The
off-gas system of the power plant Gundremmingen" published in the
May 1971 (Volume 13, No. 5) issue of Kerntechnik, pages 205-213,
especially Table 1 and 2. According to these publications, the
usual flow rates for the mixture of air, fission gases and gases
formed from water by activation, are in the range of 10-80 m.sup.3
/h at 1 atm. In the system according to the invention the quantity
of activated carbon is calculated on the basis of the fission
gases, that is, the isotopes of the noble gases, xenon and krypton,
to provide sufficient delay time in the absorptive delay section.
Taking the absorptive coefficient for xenon at normal conditions at
600-1000 cm.sup.3 /g, the amount of carbon required for this
purpose will ordinarily be in the range of 10 to 100 tons.
The voids in the activated carbon fill constitute a mechanical
delay section for the activation gases, such as the isotopes of
oxygen and nitrogen. In the case where the active carbon has
properties similar to those of the preferred form referred to
above, the void volume of the bed usually is in the range of 30 to
50% which provides sufficient delay time for the activation
gases.
The filters 36 and 37 in FIG. 4 are conventional high efficiency
filters for aerosols which are commonly used in nuclear and other
industrial ventilating systems. Examples of such devices are those
manufactured by the firm of Delbag in Berlin, Germany.
It will be understood that the above description of the present
invention is susceptible to various modifications, changes and
adaptations, and the same are intended to be comprehended within
the meaning and range of equivalents of the appended claims.
* * * * *