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ORNL-TM-1545.txt
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' -)i '.fw’
A
& ey T
AYpC
ORNL-TM- 1545
Contract No. W-7405-eng-26
General Engineering and Construction Division
DESIGN STUDY OF A HEAT-EXCHANGE SYSTEM
- FOR ONE MSBR CONCEPT
by the
GE&C Division Design Analysis Section
LEGAL NOTICE
! .
This report was prepared as an account of Gove nt sponsored c:or:fl:@::::er the United
iaten: Minien Com“mmiuion. o msl;rt::inonmfie t!:::lh;:l'I l:fptll;:d. \:lnt.b respet;t to the accu-
. Makes an ty or repre v o eat tho usa
" rac Ammpleteneiu, or usefulnesa of the information contained in this rop::‘t m:y bt e e
T of Iy.l;y information, apparatus, method, oF process -!leolod in this repo! ‘
R wned rights; or -y . e
: priva:ly‘;:mm‘ any liabllluou with respect to the use of, or for damages r:ulting from o
e e, e o Gt i 1 o
the above, ‘‘person &¢ on T
L loy::er conit:wh!‘ of fll’e Commission, or employ:ée of such eonm:lo;;n mromnm“"s.
' :nch employee or contractor of the Commission, © employe: ;t h::cemm or peerarer,
. disseminates, or provides access to, any informati F‘"““w!.. 7 oymen ‘
with the Commiasion, or his employment with such contractor. )
SEPTEMBER 1967
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee
operated by
UNION CARBIDE CORPORATION
for the
U.S. ATOMIC ENERGY COMMISSION
o A S
DISTRIBUTION OF THTS DOCUMENT IS UNTTMITED
e
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iii
The individuals who participated in this study performed by the
General Engineering and Construction Division Design Analysis Section
are listed below.
Bettis
. Braatz
Cristy
Dyslin
Kelly
Pickel
Shobe
Spaller
Stoddart
ZrPHHOUOUQDTO
OMHEX B
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CONTENTS
Abstract - * L] - ® . . . * - . . . . o . - L ’ .
INTRODUCTION . . & ¢ v o ¢ ¢ ¢ o o s o 22 o
SUMMARY . & ¢ ¢ v o ¢ a ¢« ¢ o s s s 2 o o s
DESIGN APPROACH . .+ + v v v v v o 0 v o v .
Heat-Exchange System . . « « « « « « o o « &
Factors Affecting Design of Heat Exchangers
Materials . . . . . ¢« « ¢ s ¢ o 4 .
Maintenance Philosophy . . . . . . .
Feasibility . . . . . « « + « « . .
Heat-Transfer and Pressure-Drop Calculations .
Stress Analyses . . . ¢« ¢« 4 4 4 e 4 e 0 e
DESIGN FOR PRIMARY HEAT EXCHANGERS .,
Case A . . . v ¢ v o 4 v e 4 e e e e e e e
Case B . v ¢« ¢ o & o o o o s o o s = o o
Désign Variables . . . . . . . . . . .
Calculatory Procedures . . . « « « .+ o
Results of Calculations . . . . . . .
DESIGN FOR BLANKET-SALT HEAT EXCHANGERS .
Case A . . v & ¢ ¢« o ¢ o o o o o o o o @
Case B . ¢ ¢ o ¢ ¢ v o ¢ ¢ o o o o ¢ o o o o
DESIGN FOR BOILER-SUPERHEATER EXCHANGERS .
Case A . - .. » . o - . «© . . . * » . . . . -
) Case B * . » * o . * * - L * * . ) . * o . * .
Case C B ) . . . .0 . . . . . L . - . - - .
DESIGN FOR STEAM REHEATER EXCHANGERS . . . .
Case A * » - - - . » . » » - - L4 v * * * o [ ]
caseB. . » . 4 -0 . l.l o.c . - e e . . .
- Case C * .9 - . . L . - .' .V . ', . . - . . -
Sy N W o= =
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Page
8. DESIGN FOR REHEAT-STEAM PREHEATERS . . . « « « & « o « 65
Appendix A. CALCULATIONS FOR PRIMARY HEAT EXCHANGER . . . . 71
Appendix B. CALCULATIONS FOR BLANKET-SALT HEAT EXCHANGER . 111
Appendix C. CALCULATIONS FOR BOILER SUPERHEATER | -
EXCHANGER . &« v v ¢ v ¢ ¢ o o v o o o o o s 140
Appendix D. CALCULATIONS FOR STEAM REHEATER EXCHANGER . 164
Appendix E., CALCULATIONS FOR REHEAT-STEAM PREHEATER . . 184
Appendix F. NOMENCLATURE .« &+ « « o « s o o « o« « « o & 198
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vii
LIST OF TABLES
Title
Values for Fuel-, Blanket-, and Coolant-Salt -
Properties Used in Preliminary Calculations
for MSBR-Heat-Transfer Equipment
Primary Heat Exchanger Design Data for Case A
Primary Heat Exchanger Design Data for Case B
Blanket-Salt Heat Exchanger Design Data for Case A
Blanket~Salt Heat Exchanger Design Data for Case B
Boiler-Superheater Design Data for Case A
Boiler=-Superheater Stress Data for Case B
Boiler-Superheater Design Data for Case C
Steam Reheater Exchanger Design Data for Case A
Steam Reheater Stress Data for Case B
Steam Reheater Exchanger Design Data for Case C
Design Data for the Reheat-Steam Preheater
Page
Number
15
24
33
38
43
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67
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Figure
Number
ix
LIST OF FIGURES
Title
Flow Diagram for the Case-A Heat-Exchange System
Flow Diagram for the Case-B Heat-Exchange System
Primary Fuel-Salt-to-Coolant-Salt Heat Exchanger
for Case A
Primary Fuel-Salt-to-Coolant-Salt Heat Exchanger
for. Case B
Blanket-Salt Heat Exchanger for Case A
Blanket-Salt Heat Exchanger for Case B
Boiler-Superheater Exchanger
Steam Reheater Exchanger
Reheat-Steam Preheater Exchanger
Page
Number
10
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27
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66
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4
DESIGN STUDY OF A HEAT-EXCHANGE SYSTEM
FOR ONE MSBR CONCEPT
Abstract
The heat-exchange system for one concept of a 1000-Mw(e)
nuclear power plant using a molten-salt breeder reactor has
- been studied. The system has five types of heat exchangers
to transfer the heat generated in the reactor core to the
supercritical steam energy required to drive the turbine for
the generation of electrical power. The two major design
approaches reported here are for flow circuits in which heat
- is transferred from the molten core fuel and fertile blanket
salts to the molten coolant salt and then to the supercriti-
cal fluid. The Case-A system involves relatively high fuel-
and blanket-salt pressures in the reactor core. These pres-
sures are reduced in the Case-B system by reversal of the
flows of the fuel and blanket salts through the reactor core
and the respective pumps and exchangers, while the operating
pressures of the coolant-salt system are raised above those
in the Case-A system., The criteria used, assumptions made,
relationships employed, and the results obtained in the de-
sign for each of. the five types of exchangers used in these
cases are reported. Although the resulting design for the
- Case-B heat-exchange system and the exchangers appears to
be the most workable one, further experimental and analytical
investigations are needed before the designs for these ex-
changers can be finalized.
1. INTRODUCTION
Thermal -energy molten-salt breeder reactors (MSBR) are being studied
'to assess their economic and nuclear performance and to identify important
design problems. One such study made at Oak Ridge National Laboratory
(ORNL) was of a conceptual_lOOO-Mw(e)iMBBR power plant.’ The initial
- reference design for this plant employs a molten-salt breeder reactor
with a two-region fluid-fuel ccncept that has fissile material in the
lp. R.'Kasten, E. S. Bettis, and R. C. Robertson; "Design Studies of
1000-Mw(e) Molten-Salt Breeder Reactors,' USAEC Report ORNL-3996, Oak
Ridge National Laboratory, August 1966,
core stream and fertile material in the blanket stream. This study
encompassed all of the major equipment required for a complete power
station, including the components of the heat-exchange system. The
design studies for the heat exchangers are presented here in greater
detail to document some of the unique considerations involved in the
transfer of heat between different molten-salt systems and between
molten salt and water or steam.
The reference 1000-Mw (e) plant1 has four heat-exchange loops, and
the design for this heat-exchange system is referred to here as Case A.
Five types of heat exchangers are used in this system to accomplish the
two principal transfers of heat: (1) from the fuel and blanket salts to
the coolant salt and (2) from the coolant salt to supercritical fluid.
After an evaluation of this concept was made, the possibility of'improv-
ing the system by changing the operating pressures of the fuel-, blanket-,
and coolant-salt systems became apparent. The resulting design for a
reverse-flow system with lower fuel- and blanket-salt pressures in the
reactor core and higher operating pressures in the coolant-salt system
is presented here as Case B. Because of the possibility of developing
a coolant salt with a lower and more favorable freezing-point tempera-
ture, another modification of the Case-A system was considered briefly.
This is referred to as the Case-C design. The design criteria, assump-
tions, calculatory procedures, and the resulting design data are dis-
cussed for each of the five types of exchangers in these heat-exchange
systems.
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2. SUMMARY
In the Case-A design of the heat- exchange system for the reference
1000-Mv(e) MSBR power plant, five types of heat exchangers are used in
each of the four heat- exchange loops. Each loop has one primary fuel-
salt-to- coolant salt exchanger, one blanket-salt exchanger, four boiler
superheater exchangers, two steam reheater exchangers, and two reheat-
steam preheaters to transfer the heat in the fuel and blanket salts to
the coolant salt and from the coolant salt to the supercritical fluid.
The fuel salt circulates through graphite tubes in the reactor core
with a maximum pressure of 95 psi, leaves the core, and passes through
the'primary exchanger‘where some of its heat is transferred to the cool-
ant salt. Upon leaving the primary exchanger, the fuel salt enters the
suction side of the fuel-salt pump and is_discharged back to the reactor
core. The blanket salt circulates through the reactor core outside the
graphite tubes with a maximum pressure of 115.8 psi{ Upon.leaving the
core, it passes through the blanket-salt exchanger to release some of its
heat to the coolant salt, enters the suction side of the blanket-salt
pump, and is discharged back to the reactor.
Coolant salt is circulated through the primary exchanger and the
blanket-salt exchanger in series. ‘A major portion (87%) of the coolant
salt is then circulated through the boiler superheater exchangers where
its heat is released to the supercritical fluid, while a smaller portion
(137%) of the coolant salt is circulated through the reheaters. Reheat -
steam preheaters are required in the steam system to raise the tempera-
ture of the exhaust steam from the highapressure turbine before it enters
the reheaters.
A modification of the Case-A design that would eliminate the need
for the ‘reheat-steam preheaters and_for direct-contact heating of the
supercritical'fluid before it entersuthe boiler superheaters was consid-
ered:brieflv, Case C involves lowering the 1nlet temperatures of the
steam reheaters and the boiler superheaters to study the effects of a
coolant salt with a lower freezing-point temperature.
As the studies progressed and more understanding of the overall
system was obtained, the}fact that the-pressure of the fuel salt is
. A
)
i)
higher than that of the coolant salt at the same point in the primary
exchanger and the relatively high pressures of the molten salts in con-
tact with graphite in the reactor core caused concern. The Case-B system
was developed to obtain a more desirable pressure arrangement.
In the Case-B system, the operating pressures of the coolant-salt
system were raised to assure that any leakage in the overall system
would be from the coolant-salt system into the fuel- or blanket-salt
systems. To lower the pressure on the graphite tubes in the reactor core
and keep salt penetration at a minimum, the flows of the fuel and blanket
salts through the reactor core and the respective pumps and exchangers are
reversed from those in Case A. The result is that the maximum pressure
of the fuel salt in the reactor core is 18 psi, and the maximum pressure
of the blanket salt is 32.5 psi.
The Case-B heat-exchange system involved redesign of tfie'primary,
blanket-salt, boiler superheater, and steam reheater exchangers.' The
design for the Case-B primary exchanger is an improvement over that for
Case A because the expansion bellows was eliminated and differential
thermal expansion between the inner and outer tubes is accommodated by
the use of sine-wave shaped tubes in the inner annulfis. The blanket-
salt exchanger was improved in Case B by the addition of a floating head
to accommodate differential thermal expansion between the tubes and shell
and to reduce cyclic fatigue. These improvements seem well suited for
ultimate application in the power-plant heat-exchange system.
Lo
The design criteria, calculatory procedures, and the results of the
o)
calculations for each type of exchanger are given in this report, and
many of the detailed calculations for the Case-B exéhangers are appended.
While no optimization can be claimed for these exchanger designs, we feel
that the concepts are sound and reasonable. However, there are two major
uncertainties in the heat-transfer calculations. Accurate values of the
molten-salt physical constants are not known, and the heat-transfer cor-
relations for our application need further verification. The values for
physical constants and tolerances for values of viscosity, density, and
thermal capacity that we used were provided us by the designers of the
'MSBR during the early stages of the study. Recent developments have Qfi)
revealed uncertainties in viscosity and thermal conductivity that could
)
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invalidate the existing designs. Therefore,.before final designs for the
heat exchangers can be presented with confidence, experimental investiga-
tions should be made to i
1. accurately determine the physical properties of molten fluoride salts;
2. investigate the heat-transfer properties of molten salts to extend
the work of MacPherson and Yarosh‘1
3. check and extend the heat transfer and pressure -drop equations devel-
oped by Bergelin et al.®’® to include disk and doughnut baffles;
4. 1investigate heat transfer from molten salt to supercritical fluid, in
particular the heat transfer during the transition from pressurized
water to supercritical fluid, if a practical experiment can be devised;
5. determine the tendency of both bent and straight tubes to vibrate
under various conditions of diameter, pitch,‘support, length, and
baffle shape and spacing; and to
6. determine the possible vibration effects of direct mixing of super-
critical fluid with pressurized water.
Analytical studies should also be made of the
1. possible errors to arrive at the amount of contingency that should be
designed into each exchanger to provide a trustworthy'design,
2. cyclic conditions in the system, -
3. wvibration in each exchanger to assure adeQuate tube life,
possibility of applying recently developed knowledge of tube config-
urations that enhance heat transfer,
5. 1loads on exchangers imposed by methods of support and the piping
restraints, and. R '
6. the maintenance consideratrOns.'
1R. E. MacPherson and M, M. Yarosh, 'Development Testlng'and Per-
formance Evaluation of Liquid Metal and Molten-Salt Heat Exchangers "
"Internal Document, Oak Ridge Natlonal Laboratory, ‘March 1960.
20. P. Bergelin, G. A, Brown, and A. P. Colburn, "Heat Transfer and
Fluid Friction During Flow Across Banks of Tubes -V: A Study of a Cylin-
drical Baffled Exchanger Without Internal Leakage, " Trans. ASME, 76: 841~
850 (1954).
3. Pp. Bergelin, K. J Be11 and M. D. Leighton, ”Heat Transfer and
Fluid Friction During Flow Across Banks of Tubes -VI: The Effect of Inter-
nal Leakages Within Segmentally Baffled Exchangers," Trans. ASME, 80:
53-60 (1958).
3. DESIGN APPROACH
The reference designl for the 1000-Mw(e) MSBR power plant involves
a two-region two-fluid system with the fuel salt and the blanket salt in
the reactor core separated by graphite tubes. The fuel salt consists of
uranium fluoride dissolved in a carrier salt of lithium and beryllium
fluorides, and the blanket salt contains thorium fluoride dissolved in a
similar carrier salt. The energy generated in the reactor fluid is trans-
ferred to a coolant-salt circuit that couples the reactor to a supercrit-
ical steam cycle. This reference design employs one reactor with four
heat-exchange loops. |
Since a high plant-availability factor in the'power plant is impor-
tant to the maintenance of low power costs, a modular-type design for the
MSBR plant was also considered. This modular plant would havé four sep-
arate and identical reactors with their separate salt circuits. The
desirability of the modular-type design and consideration of the size of
the components and pipe required for the reference plant influenced the
selection of the number of heat exchangers to be used in the system.
Regardless of the number of reactors to be used in the 1000-Mw(e) plant,
the study reported here is based on the use of four heat-exchange modules
in the system.
Heat-Exchange System
Each of the four modules or loops of the reference heat-exchange
system contains one primary fuel-salt-to-coolant-salt exchanger, one
blanket-salt exchanger, four boiler superheater exchangers, two steam
reheater exchangers, and two reheat-steam preheater exchangers. These
exchangers are housed in temperature-controlled shielding cells that can
be heated to temperatures up to l000°F with either gas or electric
1p. R. Kasten, E. S. Bettis, and R. C. Robertson, "Design Studies of
1000-Mw(e) Molten-Salt Breeder Reactors,'' USAEC Report ORNL- 3996 Oak
- Ridge National Laboratory, August 1966.
St
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P
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heaters. This simplifies the system considerably by eliminating the need
for auxiliary heaters on each piece of equipment and the need to insulate
each individual component.
The flow diagram of the heat-exchange system for the reference
design,l Case A,.is shown in Fig. 1. Each.heat transfer stage. consists
of a number of identical exchangers represented in Fig. 1 as a single
typical exchanger. The temperature values shown in Fig. 1 constitute
the basis from which development of the designs for the various heat
exchangers was bégun. Some of these,values‘were derived from known prop-
erties of molten-salt systems, and some were derived from simple heat
and material balances. Values in the steam system were selected to make
use of the existing steam-cycle design in the Tennessee Valley Authority's
900-Mw(e) Bull Run steam plant. This design was modified to increase the
power rating to 1000 Mv(e).
In the resu1ting design for the CaSe-A'system, the fuel salt leaving
the reactor core at a pressure of 90 psi enters the primary exchanger at
a temperature of 1300°F and a pressure of 85.8 psi and is circulated
through the tubes in the'exchanger where some of its heat is released to
the coolant salt. It then enters the suction side of the fuel-salt pump
and is dischafged back to the reactor at a temperature of 1000°F and a
pressure of 95 psi. The heat from the blanket salt is transferred to the
coolant salt in the blanket-salt heat exchanger. The blanket salt leav-
ing the reactor at a préssure of 95.8 psi enters the exchanger at a tem-
perature of 12506F afid'a pressure of 90.3 psi, is circulated through the
tubes of the exchangéf whereWSOme of its heat is given up to the coolant
salt, enters the suction sidéfbf fihe blanket-salt pump, and is discharged
back to Efierféactof_at'aitéfipefature of 1150°F and a pressure of 97.8 psi.
These transfers of heat to the coolant-salt system represent one of
the two direct stéps involvé& in converting the heat generated in the
?reactorrfiore. tO'the'energyfrqui:ed to drive the steam turbine. The
‘coolant salt in the system entérs the primary exchanger at a temperature
of'850°F and a'préssure'of779.2 psi and leaves it at a temperature of
1111°F and pressure of 28.5 psi. This coolant salt is then circulated
through the blanket-salt exchanger, entering at a temperature of 1111°F
and pressure of 26.5 psi and leaving at a temperature of 1125°F and a
ORNL DWG 67-6817
L e e e —————
i f
- P — s e e — e — . —)
! COOLANT 4 | .
| | SALT PUMP | T
| " " w
} 1 1125°F f
| . 2K Y 1 ; '
I a usoor \ GASEOUS FISSION | 5 [ |
* { - g - PRODUCTS DISPOSAL | ‘ | l
(/A . | ' SYSTEM i I
|__<‘~ ‘ ) te2s0°F Y : . I | :
n2seF | | : ' ' :] ‘
i | | : I
T | T } | ! o~ J;: I | . |
| | | | CONDENSATE
( Lo JlE o 7» I | 8 MAKE-UP
\ ~ | | REHEAT STEAM
il Y L/ | | J | PREHEATER
| | NIeF = — |000°F ' l _
¢ : ‘l 1300°F 1000°F ‘ I . :
| —— | heser 1 |
* REACTOR VESSEL 1300°F =TA
LT e R I " :
TR | : 7 BOILER REHEATER BOOSTER MIXING
BLANKET SALT \ | SUPERHEATER e PUMP TEE
HT. EXCHG. & PUMP .
A -LEGEND -
FUEL SALT
BLANKET SALT - ===
| COOLANT SALT ———~—
FUEL SALT HT. STEAM em=m=m=——-
EXCHG. & PUMP I B
Fig. 1. Flow Diagram for the Case-A Heat-Exchange System.
at
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