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**INTERMEDIATE HEAT EXCHANGE TUBE BUNDLE:**

The purpose of an Intermediate Heat Exchange Bundle is to transfer heat from the FNR primary sodium into higher pressure FNR secondary sodium. There are positions for 56 intermediate heat exchange tube bundles but only 48 of these positions are used due to the presence of physically conflicting airlock related load/unload trays. The 48 intermediate heat exchange tube bundles are immersed in the primary liquid sodium such that the upper manifold of each bundle is only half immersed. These heat exchange tube bundles isolate the radioactive primary liquid sodium from the non-radioactive secondary liquid sodium. The intermediate heat exchange tube bundles also serve as a barrier to other radioactive species in the event of a fuel tube leak. In the event of an intermediate heat exchange bundle leak the higher pressure of the secondary sodium ensures that radioactive species do not migrate from the primary sodium into the secondary sodium. In the event of a primary sodium fire the intermediate heat exchange top manifolds displace liquid sodium in a manner that prevents its combustion.

**SPECIFICATION:**

Manifold Inside Length = 4 inch = 0.1 m

Manifold OD = 38 inch

Manifold ID = 35 inch

Tubed diameter = 33.75 inch

Exposed tube length = 5.7 m

Overall tube length = 6.0 m

Tube center to center = 1.25 inch

27 tracks, 1.25 inch wide

27 X 1.25 = 27 + 6 3 /4 = 33.75 inch

547 tubes

tubes 3/4 inch ID, 7 / 8 inch OD

Manifold side wall thickness = 1.5 inch

Manifold top perimeter welded

Manifold top thickness = ?

Manifold and mating tube sheet overall length ~ 0.4 m

Contained NaK volume in tubes:

547 tubes X Pi(3 / 8 inch)^2 X 6.0 m X (.0234 m / inch)^2

= 0.9354 m^3

Contained NaK volume in manifolds:

= 2 X 0.1 m X Pi (35 inch / 2)^2 X (0.0254 m / inch)^2

= 0.1241 m^3

Total NaK volume contained in intermediate heat exchange bundle:

= 0.9354 m^3 + 0.1241 m^3

= **1.0595 m^3**

Intermediate heat exchange bundle heat transfer area:

547 tubes X Pi X (3 / 4 inch) X (0.0254 m / inch) X 5.7 m

= **186.6 m^2**

**INTERMEDIATE HEAT EXCHANGE BUNDLE SODIUM DRAIN TUBE:**

Each intermediate heat exchange bundle has a small diameter drain tube with monotonic slope running from the lowest point in the gooseneck. This tube provides nearly complete removal of NaK for service.

When it is desired to remove a particular intermediate heat exchanger argon pressure is removed from the NaK dump tank head space and is vented to the top of the secondary sodium loop. As a result the entire volume of NaK above the pool deck flows into the NaK drain down tank.

The drain tube is then used to remove NaK from the intermediate heat exchanger before disconnecting its flanges.

Hence when a heat exchanger is disconnected there will be little hazard due to residual NaK in the pipes and heat exchange bundle. Note that the pipes must slope monotonically to ensure complete NaK drainage.

The intermediate heat exchanger is realized with a single pass vertical tube bundle.

The intermediate heat exchange top manifold connects to the sodium/salt heat exchanger top manifold via a 12.75 inch OD pipe. The intermediate heat exchange bundle bottom manifold connects to the NaK-salt heat exchange bottom manifold via a 12.75 inch OD pipe. This pipe contains an induction pump and three way valve that circulate part of the NaK from the bottom of the NaK-salt heat exchanger to the bottom of the intermediate heat exchanger and part to the top manifold of the NaK-salt heat exchanger. This configuration provides controlled heat exchange counterflow and permits removal and replacement of individual components via an overhead crane lift. There is a gravity drain to the NaK dump tanks which also acts as a cushion tank.

The intermediate heat exchange bundles have round manifolds in order to permit partial rotation about the bundle axis to align their fittings with the fixed secondary sodium pipes.

The intermediate heat exchange bundles are in nearly fixed positions with respect to the concrete enclosure. When the system is at operating temperature there is about a 0.20 m gap between the secondary sodium return pipe insulation and the primary sodium pool inside wall. As the system cools this gap slowly shrinks to zero due to thermal contraction of both the primary sodium pool liner and the secondary sodium pipes.

The intermediate heat exchange tube bundle centers are located on a 18 m diameter circle coaxial with the 20 m diameter primary sodium pool. Due to relative thermal expansion this circle can shrink to being 17.6 m in diameter.

The theoretical maximum outside diameter of the intermediate heat exchange manifolds is limited to:

Pi (17.6 m) / 56 = 0.987 m = 38.872 inch

In order to allow for fabrication and positioning tolerances the Intermediate Heat Exchange Bundle manifold OD is chosen to be 38.0 inches. To provide adequate heat exchange we need a tubed diameter of 33.75 inches, which leaves:

(38 inch - 33.75 inch) / 2 = 2.125 inches

of which:

manifold side wall thickness = 1.5 inches and 0.5 inch if for the manifold inside corner radius.

Manifold side wall ID = 35 inch

The manifold top is 38 inch OD disk with a bevelled edge to permit a deep perimeter weld.

As shown on the web page titled: FNR Secondary Sodium Heat Transport System the maximum working pressure of the secondary sodium is 2.0 MPa which is set by the wall of the 16 inch diameter induction pump .

**HOOP STRESS:**

As shown on the web page titled: FNR Secondary Sodium Heat Transport System if the material is 316 SS the maximum allowed material working stress at 800 degrees K is 39 MPa.

The maximum pressure within the secondary sodium loop is constrained by the pressure withstand capabilities of the intermediate heat exchange bundle manifolds. Assume that the manifold end caps are welded. The manifold outside diameter is limited to 38 inches. The diameter of the tubed area is 34 inches. The manifold wall thickness is 1.5 inches. The manifold internal corner radius is 0.5 inches. That fully accounts for the available diameter. The hoop stress limit of the manifold perimeter wall sets the maximum possible working pressure of the secondary sodium at Pm where:
Pm (35 inch) = 39 MPa 2 (1.5 inch)

or

Pm = 39 MPa (3 / 35)

= **3.34 MPa**.

In summary the Intermediate Heat Exchange Bundle manifold has an ID of 35 inch and an OD of 38 inch. It limits the maximum working pressure of the secondary sodium to 3.34 MPa at 527 degrees C.

**GASKET CONSTRAINT:**

A major constraint on the FNR design is gasket properties. This FNR operates at too high a (temperature X pressure) product for use of normal elastomeric gaskets.

One mechanical joint seal method is to use soft metal gaskets. Such gaskets do not tolerate pipe misalignment or manifold distortion. Hence gasketed mechanical joints need close to optical precision fabrication. This precision is nearly essential for heat exchange bundle manifold fabrication. All the heat exchange bundle manifolds have welded pipes and flanges. These flanges are sealed with soft metal gaskets and bolted.

**INTERMEDIATE HEAT EXCHANGER MANIFOLD END CAPS:**

The intermediate heat exchange manifold end caps might have to be cast from Haynes 617 Alloy

**INTERMEDIATE HEAT EXCHANGE BUNDLE PRESSURE RATING:**

The intermediate heat exchange bundle should be rated for an internal working pressure of 2.0 MPa.

**INTERMEDIATE HEAT EXCHANGE BUNDLES:**

In the intermediate heat exchanger bundles the secondary sodium heat flow rate must be the same as the primary sodium heat flow rate. However, the primary sodium flow cross sectional area is larger so the primary sodium linear descent velocity is smaller.

For the intermediate heat exchanger the end face cross sectional area is:

Pi (17 inch)^2

= Pi (289 inch^2)

For the intermediate heat exchanger the tubes reduce the shell side cross sectional area by:

547 tubes X Pi (0.875 inch / 2)^2

= Pi (104.7 inch^2)

Thus for the intermediate heat exchanger the cross sectional area between the tubes is:

Pi (289 inch^2) - Pi (104.7 inch^2)

= Pi [184.3 inch^2]

= Pi [13.587 inch]^2

= Pi [27.173 inch / 2]^2

Hence the primary sodium flow into and away from the intermediate heat exchangers must be the equivalent in cross sectional area to a **27 inch nominal diameter pipe.**.

**INTERMEDIATE HEAT EXCHANGER TUBE OPEN CROSS SECTIONAL AREA:**

The intermediate heat exchange tube bundle nominally consists of 547 tubes, each 6 m long, (3 / 4) inch ID, (7 / 8) inch OD.
The cross sectional area of the rising secondary sodium in an intermediate heat exchange bundle is:

547 tubes X [Pi (0.75 inch / 2)^2] / tube

= Pi [76.92 inch^2]

= Pi [8.77 inch]^2

= Pi [17.54 inch / 2]^2

which indicates secondary sodium pipe of about 18.0 inch ID. However, from a practical system fabrication perspective 12 inch pipe is much easier to work with, so the fluid flow velocity in the tubes will be about half the fluid flow velocity in the external pipe.

**INTERMEDIATE HEAT EXCHANGE BUNDLE TUBE CONFIGURATION:**

The intermediate heat exchange tubes are Inconel 600, 20 feet (6.0 M) long. They are 0.875 inch OD, 0.750 inch ID, 0.065 inch wall thickness. The heat exchange bundles are single pass.

Note that at the edge of each intermediate heat exchange bundle liquid sodium can easily flow horizontally to as to penetrate the bundle from all sides.

**INTERMEDIATE HEAT EXCHANGE BUNDLE TUBES:**

Let Pm be the maximum working pressure of these tubes. Then:
Pm (0.7500 inch) = 2 (.065 inch)(39 MPa)

or

**Pm** = 2 (.065 inch)(39 MPa) / 0.7500 inch

= **6.76 MPa**

Note that this pressure is mich greater than the 2 MPa maximum pressure set by schedule 40S pipe and fittings.

**NaK PRESSURE DROP ACROSS THE INTERMEDIATE HEAT EXCHANGE BUNDLE:**

The induction pumps are unlikely to be more than 10% efficient.

Each loop needs at least ____ of mechanical circulating energy. If the induction pump is 10% efficient each intermediate loop needs:

5 X 0.6 kWe = 3.0 kWe

of pumping electric power. Hence the total NaK circulation pumping electricity requirement is at least:

32 X 3.0 kW = **96 kWe_________**

Allowing for flow pressure drops across the intermediate heat exchangers and the NaK-salt heat exchangers the total liquid sodium intermediate circulation pumping power will likely be of the order of 200 kWe._________

**PROCEDURE FOR INTERMEDIATE HEAT EXCHANGE BUNDLE REPLACEMENT:**

Replacing an intermediate heat exchanger involves the following steps:

a) Cool down the NaK to 120 deg C;

b) Transfer the NaK in the defective heat transport loop into the loop dump tank;

Upstream from the induction pump is a 16 inch vertical axis tee to permit complete drainage of the NaK contained within the induction pump. The lower port on this tee goes to the dump tank.
c) Disconnect both NaK service pipes at the flanged connections;

d) Immediately blank off the disconnected pipes;

e) Use the polar gantry crane to lift the defective heat exchange bundle clear of the NaK pipes and into an airlock;

f) Transfer the defective heat exchanger to a service vehicle;

g) Lift a replacement intermediate heat exchanger into place using the same air lock and crane;

h) Rotate the new heat exchange bundle so that its connection flanges align with the NaK service pipes;

k) Make pipe connections with appropriate high temperature rated metal gaskets. Use a laser alignment tool;

l) Test that the system holds argon pressure.

m) Insulate the piping;

n) Transfer NaK from the NaK dump tank back into the NaK heat transport loop;

**INLET PIPE STRESS RELIEF:**
The temperature of the NaK approaching the intermediate heat exchange inlet is about 330 degrees C. The temperature of the primary sodium near this inlet point may be over 400 degrees C. To mitigate thermal stress in the secondary sodium inlet pipe this pipe should be sleeved to reduce material thermal stress.

**INTERMEDIATE HEAT EXCHANGE BUNDLE TUBES:**

The intermediate heat exchange bundles have no shell so the diameter available for tubes is:

34 inches X 25.4 m / inch = 863.6 mm

**MECHANICAL SUPPORT:**

The weight of the intermediate heat exchangers is primarily borne by a shelf inside the primary sodium pool. This shelf is supported by steel columns with bases that rest on the inside bottom of the primary sodium pool. Each column is slightly less than:

15 m - 6 m = 9 m tall.

The intermediate heat exchange bundles are free to slide across this shelf to accommodate thermal expansion and contraction of the secondary sodium pipes and the primary sodium pool structure. The NaK pipes must be long enough to accommodate the vertical flexing associated with thermal expansion/contraction of the shelf support columns.

**FLOW CONFIGURATION:**

The intermediate heat exchangers are single pass to realize counter flow operation and to minimize material thermal stresses.

Thus in the intermediate heat exchangers higher pressure secondary liquid sodium flows inside the vertical heat exchange tubes. If there is a NaK leak from the intermediate heat exchanger that NaK will leak into the lower pressure primary sodium pool.

**INTERMEDIATE HEAT EXCHANGE BUNDLE CLEANING:**

Immediately underneath each intermediate heat exchanger is an intermediate heat exchanger gooseneck. One of the functions of this goodeneck is to trap material of a higher density than liquid sodium. Periodically when the primary sodium is hot the NaK induction pump is turned off and dirt from this gooseneck is removed by vacuum suction using a small diameter tube that runs from the bottom of this gooseneck to an isolation valve. The pressure of the argon above the NaK will drive the contents of the intermediate heat exchanger sump up the drain tube and into a catch basin, which is at ambient pressure.

**DISCONNECTION SAFETY:**

If an intermediate heat exchanger needs to be replaced the first step is to transfer all the contained NaK from this heat exchanger and its connected piping into the associated NaK dump tank. To expel NaK from the intermediate heat exchanger tubes the NaK level is first drained down to the level of the bottom of the NaK-salt heat exchanger. Then the NaK in the pipe immediately below the bottom of the NaK-salt heat exchanger blocked with a flange disc. Then argon pressure is applied to the expansion tank which will drive most of the contained NaK from the intermediate heat exchanger into the drain down tank. Then the NaK contained in the intermediate heat exchanger sump is expelled into the sump catch basin. The remaining NaK in the intermediate heat exchanger is just that remaining in the sump drain tube.

In reality, even after this procedure is complete a small amount of NaK will remain in the bottom of the intermediate heat exchanger gooseneck. This small amount still presents a potential risk to maintenance personnel and a potential fire risk if at some later time oxygen is admitted into the NaK piping. One way to minimize this risk is to remove this remanent NaK by vacuum suction. In general for safety the flanges connecting the intermediate heat exchanger and its radial piping should be closed with blanking plates while the intermediate heat exchanger is still in the reactor argon atmosphere.

**PRESSURE SAFETY:**

The NaK pressure safety rupture disk must be able to discharge any hydrogen gas from the NaK circuit at a rate equal to the maximum rate of high pressure hydrogen formation. That rate is limited by the maximum water flow through the NaK-salt heat exchanger tube rupture(s) which is a function of the heat exchange tube ID , the number of tubes ruptured and the differential pressure between the salt circuit and the NaK. Normally the NaK is at a higher pressure than the salt circuit so even if the salt circuit is full of water NaK should flow from the NaK loop to the salt circuit, not vice versa. However, we must be careful that in an emergency cooling condition automatic water filling of the salt circuit does not defeat this pressure difference._______

In a practical accident scenario the water contacting NaK forms hydrogen which raises the secondary sodium pressure until the rate of hydrogen discharge equals the rate of hydrogen formation.

Each NaK heat transport loop has expansion and dump tanks containing variable pressure argon. When the flange disc isolating the dump tank is open the dump tank also acts as an expansion tank and attenuates any pressure pulses in the secondary liquid sodium.

**INTERMEDIATE HEAT EXCHANGER OPERATING CONDITIONS:**

At normal full load the NaK temperature differential is:

450 C - 340 C = 110 deg C

without threat of NaOH precipitation.

**INTERMEDIATE HEAT EXCHANGE BUNDLE CONSTRUCTION:**

The intermediate heat exchange tubes and manifolds must be strong enough to withstand the longitudinal force exerted by the peak NaK pressure. In the event of an intermediate heat exchange tube wall failure NaK will flow through the tube rupture into the primary sodium pool. The preferred alloy for intermediate heat exchange manifold fabrication is 617 alloy. The intermediate heat exchanger mounting positions beyond a gadolinium skirt protect the intermediate heat exchange materials from neutron irradiation.

A significant issue is the overall length of the intermediate heat exchangers, including their sumps and their feed pipes. This overall length requires both sufficient overhead lifting clearance and sufficient air lock length.

Advanced Reactor Heat Exchangers reference file.The contemplated intermediate heat exchanger is realized using a 20 foot (6 m) lengths of (3 / 4) inch OD tubes. These tubes are available with sufficient wall thickness (0.065 inch) to safely withstand the maximum sodium working pressure and shear stress. The tubes terminate in 617 alloy tube sheets that form one side of the Intermediate Heat Exchange end manifolds.

**HEAT EXCHANGE BUNDLE PERFORMANCE:**

Each 6 m long intermediate heat exchange bundle has:
547 X 0.75 inch ID tubes on 1.25 inch staggered grid centers.
Within each such tube bundle there is a heat exchange area of:

547 tubes X 6 m / tube X Pi X .75 inch X 0.0254 m / inch

= 196.42 m^2

The corresponding heat flow rate per steam generator bundle limited by Inconel 600 conductivity is:
20.9 Wt / m-deg K X 196.43 m^2 X (1 / .065 inch) X (1 inch / .0254 m) = 1,231,872 Wt / deg K

= 2.487 MWt / deg K

Thus temperature drop across the heat exchange bundle tube wall is:

(1000 MWt / 48) / (2.487 MWt / deg K)

= 8.377 deg C

However, there will be a further reduction in intermediate heat exchanger performance because the primary side of the intermediate heat exchanger operates in the laminar flow region. The effective tube wall thickness is increased by about (1 / 16) inch of sodium. At 700 deg K the liquid sodium has a thermal conductivity of 70.53 W / m-deg K.

Hence the temperature drop delta T across the (1 / 16) inch thick liquid sodium boundary layer is given by:

1000 X 10^6 Wt / 48 intermediate heat exchange bundles = [(delta T) (70.53 Wt / m-deg K) X 547 tubes bundle X 6 m X Pi X (7/8 inch)] / [(1 / 16) inch]

or

(delta T) = {[1000 X 10^6 Wt][(1 / 16) inch]} / [{(48 bundles) X (70.53 Wt / m-deg K) X (547 tubes / bundle) X 6 m X Pi X (7 / 8 inch)]

= **2.05 deg K**

Hence the total temperature drop across the intermediate heat exchange bundles at full power is about:

8.377 deg C + 2.05 deg C = 10.42 deg C.

A key issue is whether there is enough natural circulation of secondary sodium with 110 degree C oil in the NaK-salt heat exchanger to remove fission product decay heat.

The differential pressure established by the falling sodium column is:

P = [(873.2 -849.4) / 2] kg / m^3 x 6 m x 9.8 m / s^2

= 699.72 kg m / s^2-m^2

Neglecting viscosity:

P = Rho V^2 / 2

or

V = [2 P / Rho]^0.5 = [2 (699.72 kg m / s^2-m^2) / (849.4 kg / m^3)]^0.5 = 1.2836 m / s

= maximum possible falling sodium flow velocity

The corresponding maximim falling sodium volumetric flow rate through 12 inch ID pipe is:

= 1.2836 m / s X Pi (6 inch)^2 X (0.0254 m / inch)^2

= 0.0937 m^3 / s

Under these circumstances the NaK temperature differential will be about 300 degrees C.

Hence the heat flux through the secondary sodium piping will be about:

300 degrees C X 0.0937 m^3 / s X 856 kg / m^3 X 1.26 kJ / kg deg C

= 30318 kJ / s

= 30.3 MWt

However this heat flux will be reduced by the secondary sodium viscosity.

It is necessary to maintain the design temperature differential across the reactor in order to develop the required primary sodium natural circulation through the reactor.

Each intermediate heat exchanger transfers up to 21 MWt of heat which in turn can provide up to 6.25 MWe of turbo-electricity generation. Thus the total reactor electricity output is limited by the heat transport system to about:

48 X 6.25 MWe = **300 MWe**

**NaK Loop:**

The NaK discharge temperature from the intermediate heat exchange bundle is about 450 degrees C at full load and 460 degrees C at low load. The NaK return temperature from the sodium-salt heat exchanger is about 340 degrees C at full load and 322 degrees C at low load. There is a NaK drain to the pressure rated NaK dump tank at a low point on the NaK return pipe between the NaK-salt heat exchanger and the intermediate heat exchange bundle. The drain pipe is connected so as to fully drain the induction pump and three way valve.

**TEMPERATURE CONSTRAINT:**

At low steam loads the NaK flow through the intermediate heat exchanger will decrease and the NaK discharge temperature from the intermediate heat exchange bundle will rise about 459 degrees C. As the steam load increases the NaK flow through the intermediate heat exchange bundle will increase and the NaK discharge temperature from the intermediate heat exchange bundle will decrease to about 450 degrees C.

As the primary liquid sodium flows through the reactor at full power its temperature increases from 410 C to 460 C. The fuel tubes must contain no nickel to avoid fuel tube enbrittlement which will otherwise occur in this temperature range.

**NaK HEAT TRANSPORT:**

Define:

Fmi = NaK mass flow rate (kg / s);

Cpi = NaK heat capacity

= 1.26 kJ / kg-deg K for sodium

Delta Ti = change in NaK temperature

= 450 C - 340 C = 110 deg K

Then for sodium:

Fmi Cpi (Delta Ti) = 1000 MWt

or

Fmi = [1000 MWt] / [Cps (Delta Ti)]

= {[1000 MWt]

/ [(1.26 kJ / kg-deg K) (110 deg K)]} X {1 kJ / kWt-s} X {10^3 kWt / MWt}

= [(1000) / (1.26 X 110)] X 10^3 kg / s

= **7.215 tonnes / s**

The corresponding volumetric NaK flow is:

(7.215 tonnes / s) / (0.856 tonnes / m^3

= **8.429 m^3 / s**

Since there are 48 intermediate heat exchangers, the required intermediate sodium volume flow rate in each exchanger is:
(8.429 X m^3 / s) / 48 exchangers

= **0.1756 m^3 / s-exchanger**

The 12.75 inch OD Schedule 40S pipe has a 12.000 inch ID.

Its inside cross sectional area is:

Pi (6 inch X 0.0254 m / inch)^2
= 0.073 m^2

Thus at full load the average NaK flow velocity in this pipe is:

(0.1756 m^3 / s) / (0.0753 m^2) = **2.332 m / s**

Note that the fluid cross sectional area in the intermediate heat exchange bundle is about twice the cross sectional area in the secondary sodium piping. Hence on exiting the intermediate heat exchanger the NaK must be accelerated. The same eeffect also sapplies to secondary sodium exiting the NaK-salt heat exchanger. These two accelerations add to the NaK loop pressure drop.

**VISCOSITY COMPENSATION:**

The following equations derived on the web page titled FNR PRIMARY SODIUM FLOW can be used to find the pressure drop Pd per round coolant flow tube neglecting natural circulation:

**Fv = [Pi Pd Ro^4] / [Muv Zo (N + 2)(N + 4)]**BR>
where:

Pd = pressure drop along tube in Pa (1 Pa = 1 kg m /s^2 m^2)
Fv = volumetric flow rate / tube
Pi = 3.14159

Ro = (0.37 inch / 2) X (0.0254 m / inch) = 0.004699 m = tube inside radius

Muv = 3 X 10^-4 N-s / m^2 = sodium viscosity

(N + 2) = Ro [(Rhos Pd) / 2]^0.25 [1 / [Muv Zo]^0.5]

where:

Zo = 6.0 m = tube length

Rhos = 849.4 kg / m^3 = density of sodium at the reactor operating temperature

Recall that:

Fv = [Pi Pd Ro^4] / [Muv Zo (N + 2)(N + 4)]

or

**Pd = [Fv / (Pi Ro^4)] [Muv Zo (N + 2)(N + 4)]** Equation #1

Recall that:

(N + 2) = Ro [(Rhos Pd) / 2]^0.25 [1 / [Muv Zo]^0.5]

or

**N = {Ro [(Rhos Pd) / 2]^0.25 [1 / [Muv Zo]^0.5]} - 2** Equation #2

Try and initial interim value of N = 1.0 in equation #1 and solve for an interim value of Pd.

Substitute that interim value of Pd into equation #2 and solve for a new interim value of N.

Repeat this process itteratively until N and Pd converge.

Then the sum of the Pd values in combination with the exchanger intermediate sodium flow rate give the mechanical load for an ideal circulation pump.

**INTERMEDIATE HEAT EXCHANGE TUBE CONFIGURATION:**

The intermediate heat exchange tubes are Inconel 600, 20 feet (6.1 M) long. They are 0.87500 inch OD, 0.065 inch wall thickness. The intermediate heat exchange bundles are single pass and configured for complete drainage to the secondary sodium dump tank.

Assume that the intermediate heat exchange tubes are located on 1.25 inch staggered grid to allow external primary liquid sodium to easily penetrate the tube bundle.

**INTERMEDIATE HEAT EXCHANGE BUNDLE WEIGHT:**

Inlet Pipe = ____

Discharge Pipe = ____

Drain tube = _____

2 X Pipe Flange = _____

2 X Manifold cover = ______

2 X Manifold wall =
2 X Manifold Tube Sheet= _______

Tubes =

Pi [(0.875 inch)^2 - (0.75 inch)^2][1 / 4] X (0.0254 m /inch)^2 X 6.1 m / tube X 547 tubes X (7600 kg_____ / m^3)

= 4621.36 kg______

Total empty Intermediate Heat Exchange Bundle Weight = _______

**CONSTRUCTION:**

The secondary sodium piping is 12.75 inch OD. The drain down tanks are formed from 24 inch diameter ________pressure pipe. It has an external electric heater, similar to the heating element on an electric domestic hot water tank, for startup sodium melting.

**INSTALLATION:**

The intermediate heat exchangers are installed in the primary sodium pool by lowering using the overhead gantry crane. Each unit is supported by a shelf. The connected pipes are supported by hangers with threaded hardware for precise height adjustment. The flange connection height is adjusted for accurate alignment between the intermediate heat exchange bundle and the secondary sodium pipes to the heat exchange gallery.

**FNR INTERMEDIATE HEAT EXCHANGE TUBES:**

This web page deals with FNR intermediate heat exchanger tubes. These tubes are not surrounded by a shell and hence are free to expand and contract in their operating temperature range 330 degrees C to 520 degrees C.

It is shown that due to best performance under severe thermal stress the best heat exchange tube material for the intermediate heat exchangers is likely Inconel 600 or 617 alloy.

**MATERIAL PROPERTIES:**

Define:

TC = thermal conductivity

TCE = thermal coefficient of expansion

DeltaT = temperature drop across steel tube wall

Y = (stress / strain) = Young's modulus

Sy = yield stress

Key material properties are set out in the following table:

PROPERTY | 316L | HT-9 | D9 | 15/15Ti | INCONEL |
---|---|---|---|---|---|

Density | 7966 kg / m^3 | 8200 kg / m^3 | 8430 kg / m^3 | ||

TC @ 500 C | 15 W / m-K | 26.2 W / m-K | 20.2 W / m-K | 20.9 W / m-K | |

TCE @ 500 C | 18 X 10^-6 / K | 15 X 10^-6 / K | 13 X 10^-6 / K | 15.1 X 10^-6 / K | |

Y @ 25 C | 202 GPa | - | -- | 207 GPa | |

Y @ 250 C, no rad. | - | 2000 GPa | -- | -- | |

Y @ 250 C, with rad. | 2000 GPa | -- | -- | ||

Y @ 350 C, no rad | 860 GPa | ||||

Y @ 350 C, with rad | 1200 GPa | ||||

Bulk Y @ 500 C | 120 Gpa | 135 GPa | -- | ||

Sy @ 25 C, no rad. | 291.3 MPa | - | -- | 630 MPa | 550 MPa |

Sy @ 250 C, no rad. | 600 MPa | - | 570 MPa | - | |

Sy @ 250 C, rad | 900 MPa | - | - | ||

Sy @ 350 C, no rad. | 420 MPa | 560 MPa | - | ||

Sy @ 400 C, rad | 600 MPa to 900 MPa | - | - | ||

Sy @ 465 C, no rad | 725 MPa | - | 530 MPa | - | |

Sy @ 460 C, with rad | 520 MPa | - | - | ||

Sy @ 500 C, no rad | 167 MPa | 400 MPa to 550 MPa | 510 MPa | 579 MPa | |

Sy @ 500 C, with rad | 450 MPa to 600 MPa | - | - | ||

-- | -- | -- | - |

**INTERMEDIATE HEAT EXCHANGE TUBE MATERIAL:**

The optimum choice of heat exchange tube material for an FNR is a complex property tradeoff. A practical consideration is that the tube walls must be sufficiently robust to withstand the stress associated with internal sodium freezing and then remelting.

Another practical consideration in choosing the heat exchange tube material is its workability. Each FNR has ~ 52,512 heat exchange tubes containing secondary sodium that must be automatically fabricated, assembled and tested.

The heat exchange tube alloy must be chemically compatible with Na, H2O, UO2, U, Pu, Zr, fission products, transuranium actinides from 20 degrees C to 530 degrees C.

**PRESSURE AND THERMAL STRESSES:**

Due to the internal pressure an intermediate heat exchange tube wall is under tension. The material pressure stress is partially balanced by the radial heat flux which changes the stress distribution. Net stress will over time cause intermediate heat exchange tube material creep and hence heat exchange tube diameter increase.

<0.030% C + <1.00% Si + <2.00% Mn + <0.045% P + <0.015% S + <0.11% N

+ {16.5% Cr to 18.5% Cr + 2.00% Mo to 2.500% Mo + 10% Ni to 13% Ni + Fe}

or + {17.0% Cr to 19.0% Cr + 2.50% Mo to 3.00% Mo + 12.5% Ni to 15% Ni + Fe}

or

+ {16.5% Cr to 18.5% Cr + 2.50% Mo to 3.00% Mo + 10.50% Ni to 13.00% Ni + Fe}

**FOR 316L STAINLESS STEEL HEAT EXCHANGE TUBES:**

Thermal Stress:

**(DeltaT)**

= (Sy)(2) / [(TCE) Y]

= [24,400 psi(2) X (101,000 Pa / 14.7 psi)] / [ (17.5 X 10^-6 / deg C) X (202 X 10^9 PA)]

= [48.8 X 101 X 10^12 deg C] / [14.7 X 17.5 X 2.02 X 10^11]

= 94.80 deg C

For a conservative safe design the maximum thermal stress and hence the maximum operating temperature differential should be reduced by a factor of three to: 31.60 deg C

However, there is also differential pressure stress. If the stresses are to be equally divided between differential temperature and differential pressure the maximum differential temperature across the tube wall further decreases to 15.8 C.

Thus the maximum operating heat flux through the 316L stainless steel tubes is:

15.8 deg C X 15 W / m-deg C / (.065 inch X .0254 m / inch) = **143,549.4 W / m^2**

The intermediate heat exchange tube area is:

Pi X (.500 inch) X (.0254 m / inch) X 6.0 m / tube X 32 bundles X 1084 tubes / bundle

= **8304 m^2**

Hence the corresponding maximum possible reactor thermal power is:

143,549 W / m^2 X 8304 m^2 = 2092,854,595 Wt

= **1,192.0 MWt**

In reality the maximum reactor power will be limited by the liquid sodium flow between the reactor core fuel tubes.

The corresponding allowable differential pressure P is given by:

P (.37 inch) = (Syp / 6) 2 (.065 inch)

or

**P** = (Syp / 6)(0.13 inch / 0.37 inch)

= 30,000 psi (.05855)

= 1756.7 psi

= 119.5 bar

= **12.07 MPa**

**OTHER TUBE ALLOYS CONSIDERED:**

Look at 617.

**316** According to Gimondo 316 consists of:

{Fe + 0.05% C + 17% Cr + 2.0% Mo + 0.6% Si + 1.8% Mn + 13% Ni + 20 ppm B}

**316 Ti** is an austenitic stainless steel alloy described by Gimondo as consisting of:

{Fe + 16% Cr + 2.5% Mo + 14% Ni + 0.6% Si +1.7% Mn + 0.05% C + 0.4% Ti +0.03% P}

**D9** is a titanium stabilised austenitic stainless steel Indian alloy described by Leibowitz and Blomquist as consisting of the weight percentages:

{65.96% Fe + 13.5% Cr + 2.0% Mo + 15.5% Ni + .04% C + 2.0% Mn + 0.75% Si + 0.25% Ti}

and described by Banerjee et al as:

{Fe + 14.7% Cr + 2.2% Mo + 14.9% Ni + .05% C + 1.3% Mn + 0.65% Si + 0.18% Ti

+ <.05% Cu + <.07% Nb + .045% V + .03% Co + <.034% Al + <.004% Sn + .005% W + <.04% N + .008% P + .005% S + <.006% As}

and is described by Karthik et al as:

{Fe + 13.5% to 14.5% Cr + 2% Mo + 14.5% to 15.5% Ni + .035% to .05% C + 1.65% to 2.35% Mn + 0.5 to 0.75% Si + 0.2% Ti}

and is described by Gimondo as consisting of:

{Fe + 13.5% Cr + 2.0% Mo + 15.5% Ni + .04% C + 2.0% Mn + 0.75% Si + 0.25% Ti}

The alloy D9 features a higher creep rupture strength, a lower creep rate and a lower rupture ductility than 316L.

**15/15 Ti (12R72)** is an austenitic stainless steel European alloy described by Gimondo as consisting of the weight percentages:

{Fe + 15% Cr + 1.2% Mo + 15% Ni + 0.10% C + 1.5% Mn + 0.6% Si + 0.4% Ti + 0.03% P + 50 ppm B}

15/15 Ti (12R72) has an approximate fast neutron dose limit of 120 dpa. It has a Larson Miller parameter of 23.8 at 100 MPa.

**OTHER ALLOY PROPERTIES:**

**9Cr - 1 Mo steel** has a well documented creep rupture life.

**T91** is a ferritic-martensitic steel with Larsen Miller parameter 21.5 at 100 MPa.

A major issue with Austenitic stainless steel such as 316 used at 420 C is that under prolonged fast neutron exposure it swells as much as 25% whereas under the same neutron exposure ferritic steels expand < 1%. This swelling will reduce the flow of cooling liquid sodium through the reactor core.

**HEAT EXCHANGE TUBES:**

**Inconel 600** is a high nickel alloy that maintains its yield stress rating at high temperatures and hence is widely used in high temperature heat exchangers where there may be both substantial pressure differences and high thermal stress. It is described by American Special Metals and Rolled Alloys Inc. as:

> 72% Ni (+ Co) + 14.0% to 17.0% Cr + 6.00% to 10.00% Fe + < 0.15% C + < 1.0% Mn + < 0.015% S + < 0.50% Si + < 0.50% Cu

Inconel-600 is only used in heat exchangers that are outside the neutron flux. The inconel 600 must be chemically compatible with Na and H2O at 100 to 500 degrees C.

**FOR INCONEL 600:**

**(DeltaT)** = (Sy)(2) / [(TCE) Y]

= [579 MPa (2)] / [ (15.1 X 10^-6 / deg C) X (207 X 10^9 Pa)]

= [1158 X 10^6 Pa deg C] / [15.1 X 207 X 10^3 Pa]

= 370.5 deg C

For a conservative safe design the maximum stress and hence the maximum operating temperature differential should be reduced by a factor of three to: 123.5 deg C

In order to allow for half the allowable stress being due to internal pressure further reduce the operating temperature differential by another factor of two to 61.75 degrees C.

Thus the conservative operating heat flux through the Inconel 600 tubes of the primary to secondary heat exchanger is:

61.75 deg C X 20.9 W / m-deg C / (.065 inch X .0254 m / inch) = **781,693 w / m^2**

The heat exchange tube surface area is:

Pi X (.500 inch) X (.0254 m / inch) X 5.5 m / tube X 1084 tubes / bundle X 32 bundles = **7612 m^2**

The maximum allowable internal gas pressure causes a hoop stress of:

(Sy / 6) = 24,400 psi / 6

= 4067 psi.

(Max Pressure) X (.500 inch - .130 inch) X L = 4067 psi X 2 x .065 inch X L

or

Maximum pressure = 4067 psi X .130 inch / .37 inch

= 1429 psi

= **97.2 bar**

**CHEMICAL STRESS:**

The heat exchange tubes used in the sodium-salt heat exchanger are also subject to stress due to bing in continuous contact with molten nitrate salt. This issue impacts the choice of heat exchange tube alloy.

**STRESS ISSUES:**

Another major constraining issue is the combined thermal stress and internal pressure stress in the tubes which form the intermediate heat exchanger. In addition to internal pressure the intermediate heat exchanger has a significant temperature differential across the tube wall. This temperature differential can potentially lead to high thermal stress at the point where the cool return NaK is first heated by the primary liquid sodium. This problem is minimized by keeping the primary liquid sodium temperature stratified.

One of the issues with Inconel is long term creep. This issue is particularly important in the intermediate heat exchanger.

**PRESSURE AND THERMAL STRESSES:**

Due to the internal pressure the inside of an intermediate heat exchange tube wall is under tension. The radial heat flux places the inside of the tube wall under compression and the outside of the tube wall under tension. Net stress will over time cause intermediate heat exchange tube material creep and hence cause the heat exchange tube diameter increase.

**CREEP AND THERMAL STRESS:**

Another major constraining issue is the combined thermal stress and internal pressure stress in the tubes which form the intermediate heat exchanger. In addition to internal pressure the intermediate heat exchanger has a significant temperature differential across the tube wall. This temperature differential can potentially lead to high thermal stress at the point where the cool secondary return sodium is first heated by the primary liquid sodium. This problem is minimized by keeping the primary liquid sodium temperature stratified.

One of the issues with Inconel is long term creep. This issue is particularly important in the intermediate heat exchanger. To minimize the effect of long term creep on primary sodium flow the tubes in the intermediate heat exchanger are arranged in a square lattice rather than a staggered lattice and the tube center to center distnace is made 1.00 inch.

**INTERMEDIATE HEAT EXCHANGE BUNDLE REPLACEMENT PROCEDURE:**

The heat exchange bundle replacement procedure is similar to the fuel bundle installation and removal procedure except that different air locks are used that have different dimensions, different size doors and different auxiliary equipment. These other airlocks are also used to enable occasional worker access to the space above the primary sodium pool deck and to allow occasional replacement of open steel lattice, secondary sodium piping and gantry crane components.

**The heat exchange bundles with their associated piping and flanges are taller than the fuel bundles. Hence the height of the gantry crane hook above the top of the NaK pipes is set by the height of the heat exchange bundles. To mitigate this height issue the NaK pipes are run horizontally as close as practical to the pool deck.**

Intermediate heat exchange bundles are transported in the horizontal position on flat deck trucks with their tops near the back of the truck. From a truck deck a heat exchange bundle is winched into an airlock.

** INTERMEDIATE HEAT EXCHANGE BUNDLE REPLACEMENT:**

In order to replace an intermediate heat exchange bundle it is unbolted, lifted vertically 8 m, moved to an equipment transfer airlock loading ramp, rotated so that its axis is horizontal and then moved horizontally into an equipment transfer airlock.

This web page last updated April 25, 2022

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