8.4. Fuel-pin Failure Criteria

DEFORM‑4 contains a number of methods for the determination of fuel‑pin failure and failed pin model initiation. These can be divided into two major areas: (1) failure based on specified conditions, and (2) calculated failure correlations. The first method is currently used to produce failure initiation because of the limited amount of integral code validation with the failure correlations. Since these use parameters such as stress and temperature to produce the predictions, it is essential that these be checked against experimental tests to assure the accuracy and appropriateness of their use under various transient conditions. The first method involves parameters used previously with the SAS3D code system, so some familiarity with their use and limitations is assumed. Although these are simple, they can be used in a manner consistent with the SAS3D implementation and available experimental data.

All criteria are cast into the form of a failure fraction, which is the current value for the parameter being used as a failure indicator, i.e., melt fraction, time, etc., divided by the value which would produce failure. If this failure fraction becomes 1, then failure is assumed to occur and the failed pin modeling is initiated. In addition to satisfying the parameter under consideration, the fuel melt fraction must be above a specified level, FMELTM, before PLUTO2 or LEVITATE will be initiated. These calculations are performed in the subroutine CLDFAL.

8.4.1. Input Specified Failure Criteria

Through the use of the input parameters MFAIL, IFAIL, JFAIL, FSPEC, and FMELTM the code can be controlled to initiate failure with the conditions discussed below. MFAIL selects the meaning of FSPEC, IFAIL and JFAIL specify the radial and axial location of the test for failure, and FMELTM is the minimum melt fraction necessary at the location of failure for PLUTO2 or LEVITATE to be initiated. Table 8.4.1 gives the selections currently available in conjunction with DEFORM-4. If IFAIL and JFAIL are not specified, the location of the parameter maximum is selected.

Table 8.4.1 Failure Initiation Options

MFAIL

FSPEC

IFAIL

JFAIL

1

Time

Nec*

2

Temperature

Nec

Opt**

3

Melf fraction

Opt

4

Cavity pressure

Opt

5

Hoop stress

Opt

7

Rip propagation

Opt

*Nec = Necessary parameter that must be specified.

**Opt = Optional parameter. If not specified, the axial level with the maximum value will be chosen.

The use of MFAIL with a value of 7 initiates the failure with a criteria that is consistent with the LEVITATE and PLUTO2 rip propagation considerations, see Section 16.3.1 and Section 14.3.3, respectively. This criterion checks the cladding hoop stress introduced by a molten cavity pressure, for fully cracked fuel, or fuel‑cladding mechanical interaction, when solid fuel is present, against the ultimate tensile strength of the cladding to determine if failure has occurred. If the cladding does fail, then the routine checks to see if the molten fuel has reached the crack boundary. Both conditions are necessary for the initiation of the failed fuel routines.

When other failure criteria are used, there may be extensive rip propagation after initiation of the failed fuel model because of the change in criterion.

8.4.2. Calculated Failure Correlations

In DEFORM‑4, there exist a number of failure correlations that may be used to determine the time and location of cladding failure. Care should be taken when drawing any conclusions based on these correlations, since the validation effort is in its initial stages with these correlations. In addition, the method of determining cladding stress is not totally consistent between DEFORM‑4, a more mechanistic approach, and the correlations, which were based on initial cold dimensions and fill‑gas pressures. DEFORM‑4 also considers fuel‑cladding mechanical interaction rather than just gas pressure.

The use of these failure correlations currently involves an iterative approach, using the failure fractions printed by SAS4A and one of the failure conditions described in Section 8.4.1. First, the case is run with no failure conditions specified and restart files produced at selected intervals. The output is then studied to determine when the failure fraction of interest reaches one, and at which axial segment. One of the conditions discussed above is then selected to initiate failure at the appropriate time and axial segment. A restart case is then run from a restart file produced before the correlation failure condition was reached. In this case, one of the simple failure criteria will be used to initiate failure. The values used in the simple criteria should be chosen to produce failure initiation at the same time and place as was predicted by the correlation criterion during the initial run.

The various correlations are given below. Although the units are inconsistent in many cases, the code has taken this into account and made the necessary adjustments.

8.4.2.1. Biaxial Stress Rupture

This correlation is from the Nuclear Systems Material Handbook [8-17] and is based on unirradiated, 20% cold‑worked type 316 SS developmental cladding.

(8.4‑1)

\[\log \theta = - 15.22 + 9.5342 \log \left\lbrack \log \left( \frac{\sigma^{*}}{\sigma} \right) \right\rbrack\]

where

\(\theta\) = Dorn parameter = \(t_{\text{r}} \exp\left(\frac{-Q}{RT} \right)\)

\(t_{\text{r}}\) = Rupture time, hr

\(T\) = Temperature, K

\(Q\) = 83,508 cal/mole

\(R\) = Universal gas constant

\(\sigma\) = Hoop stress = \(\frac{r_{\text{o}}^{2} + r_{\text{i}}^{2}}{r_{\text{o}}^{2} - r_{\text{i}}^{2}} P\) , ksi

\(\sigma^{*}\) = 135 ksi

\(r_{\text{o}}\) = Clad outer radius

\(r_{\text{i}}\) = Clad inner radius

\(P\) = Internal gas pressure (or interface pressure), ksi

8.4.2.2. Burst Pressure

This correlation is from the NSMH [8‑17] for unirradiated FTR cladding.

(8.4‑2)

\[P = \sum_{\text{i} = 0}^{10} a_{\text{i}} \sigma^{i}\]

where

\(P\) = Burst pressure, ksi

\(\sigma\) = Hoop stress, as defined above

\(a_{0} = 1.799988 \times 10^{1}\)

\(a_{1} = 2.866442 \times 10^{-2}\)

\(a_{2} = -3.986012 \times 10^{-4}\)

\(a_{3} = 2.408207 \times 10^{-6}\)

\(a_{4} = -8.090292 \times 10^{-9}\)

\(a_{5} = 1.607218 \times 10^{-11}\)

\(a_{6} = -1.962158 \times 10^{-14}\)

\(a_{7} = 1.487159 \times 10^{-17}\)

\(a_{8} = -6.821934 \times 10^{-21}\)

\(a_{9} = 1.735220 \times 10^{-24}\)

\(a_{10} = 1.879417 \times 10^{-28}\)

8.4.2.3. Transient Burst Temperature

This correlation is from the NSMH [8‑17] for unirradiated cladding. It involves two temperature ramp rates, 5.56 and 111.1 K/s. If the rate is between these, a linear interpolation is performed.

(8.4‑3)

\[T_{\text{f}} = 2358.4 - 36.41 \sigma + 0.5649 \sigma^{2} - 3.455 \times 10^{- 3} \sigma^{3}\]

for \(\dot{T} \leq 5.56\) K/s

(8.4‑4)

\[T_{\text{f}} = 2484.8 - 37.80 \sigma + 0.5827 \sigma^{2} - 3.585 \times 10^{- 3} \sigma^{3}\]

for \(\dot{T} \geq 111\) K/s

where

\(T_{\text{f}}\) = Failure temperature, °F

\(\Sigma\) = Hoop stress, as defined above

8.4.2.4. Larson-Miller Life Fraction

This correlation is the LMP life fraction incorporated in the TEMECH computer code [8‑30].

(8.4‑5)

\[\log \left( \frac{t_{\text{r}}}{3600} \right) = \frac{\text{LMP}}{1.8 T} - C\]

where

\(t_{\text{r}}\) = Time to rupture, in seconds

\(C\) = Material-dependent constant = 20

LMP = Experimentally determined Larson‑Miller parameter

\(T\) = Cladding temperature, K

For 20% CW 316 SS cladding, the following correlation is used.

(8.4‑6)

\[\text{LMP}' = 4.6402 - 5.1218 \times 10^{-2} \sigma_{\text{m}} + 7.0417 \times 10^{-4} \sigma_{\text{m}}^{2} - 4.1349 \times 10^{-6} \sigma_{\text{m}}^{3}\]

for \(0 \leq\) fluence \(\leq 1.9 \times 10^{22}\)

(8.4‑7)

\[\text{LMP}' = 4.2281 - 2.0469 \times 10^{-2} \sigma_{\text{m}}\]

for \(1.0 \times 10^{22} < \text{ fluence } \leq 3 \times 10^{22}\)

(8.4‑8)

\[\text{LMP}' = 7.488 - 0.138 \sigma_{\text{m}}\]

for \(5.56\) K/s temperature ramp and fluences between \(3.0 - 4.0 \times 10^{22}\)

(8.4‑9)

\[\text{LMP}' = 5.285 - 7.778 \times 10^{-2} \sigma_{\text{m}} + 6.027 \times 10^{-4} \sigma_{\text{m}}^{2}\]

for \(111.1\) K/s temperature ramp and fluences between \(3.0 - 4.0 \times 10^{22}\)

where

\(\text{LMP} = \text{LMP}' \times 10^{4}\)

\(\sigma_{\text{m}}\) = Modulus modified hoop stress in ksi = \(\sigma_{\text{c}} \frac{E \left( 1033C \right)}{E \left( T \right)}\)

These rupture times are then used in the life fraction form as

(8.4‑10)

\[\text{life fraction} = \sum_{\text{i}}\frac{\Delta t_{\text{i}}}{t_{\text{r,i}}}\]

where

\(i\) = Time-step number

\(\Delta t_{\text{i}}\) = Time-step length

\(t_{\text{r,i}}\) = Time for cladding rupture

8.4.3. Preliminary Metal Fuel Failure Criteria

The consideration of a new fuel type in the context of DEFORM and SAS4A raises the question of the type of failure these pins will experience. Because metal fuel does not produce the same magnitude of fuel-cladding mechanical interaction as the oxide fuel, it is reasonable to assume that the cladding failure will result from a different phenomenon.

Metal uranium forms a low melting point eutectic alloy with both iron and nickel, constituent materials in the cladding alloys used. As the steady state irradiation proceeds, the iron and nickel can be leached out of the cladding, leading to the formation of a low melting point alloy layer adjacent to the cladding surface. Under transient conditions the temperature in this outer layer, at a certain axial location, may become high enough to melt this material. This in turn can produce a failure at this location by accelerating the further thinning of the load bearing cladding. A number of tests with UFs rods were performed and analyzed to develop a correlation for the time to cladding failure [8-31]. This correlation has been incorporated into the FAILUR routine for preliminary use until a more mechanistic model is developed which handles the cladding thinning and subsequent failure from the local pressure.

(8.4‑11)

\[T_{\text{f}} = 9.142 \times 10^{4} \left\lbrack \frac{T_{\text{a}}}{T_{\text{cut}}} \right\rbrack^{-28.495} \left( 1 + B \right)^{- 0.54669}\]

where

\(T_{\text{f}}\) = Time to failure at the current conditions, s

\(T_{\text{a}}\) = Temperature at the fuel-cladding interface, °C

\(T_{\text{eut}}\) = Input eutectic temperature, °C

\(B\) = Burnup, atom percent

Once this time has been determined, a life fraction approach is used by dividing the current time step by this failure time and adding it to the previously calculated fractions. When the fraction reaches 1, failure is assured.

(8.4‑12)

\[F_{\text{f,n}} = F_{\text{F,O}} + \frac{\Delta t}{T_{\text{f}}}\]

where

\(F_{\text{f,n}}\) = New life fraction value

\(F_{\text{f,o}}\) = Sum of previous life faction values

\(\Delta t\) = Time step, s

This correlation was developed over a narrow range of temperatures so its use should be considered preliminary until a more mechanistic approach is developed.

8.4.4. Failure Modeling Coupling to Fuel Motion Models

In order to correctly assess the accident scenario in a transient that leads to fuel pin failure and subsequent fuel motion, there should be a high degree of consistency between the methods for predicting the initial failure and that used to predict the axial propagation of this failure. This consistency has now been incorporated in the FAILUR subroutine for the option with MFAIL equal to 6. While the actual criterion used is preliminary in nature, the fact that consistency exists between failure and rip propagation is important in order to study how this affects the accident scenario. It is noted that his consistent failure model has been implemented only for an oxide-fuel type failure. A similar consistent failure model for the metal fuel pins will be added in the future.

PLUTO2 and LEVITATE use a rip propagation model that compares the circumferential cladding stress, induced by a pressurized molten cavity acting on cracked fuel, to the ultimate tensile strength of the cladding. A stress greater than the ultimate tensile strength produces failure at the axial location. This same approach has been followed in this failure prediction.

First, the SAS4A/DEFORM cladding node structure is converted to one compatible with to the failed fuel modeling routines. PLUTO2 and LEVITATE divide the cladding into an inner cladding node containing three-fourths of the cladding thickness, and an outer node containing the rest.

(8.4‑13)

\[r_{\text{c}1} = r_{\text{ci}} + 0.25 \left( r_{\text{co}} - r_{\text{ci}} \right)\]

(8.4‑14)

\[r_{\text{c}2} = r_{\text{ci}} + 0.75 \left( r_{\text{co}} - r_{\text{ci}} \right)\]

where

\(r_{\text{c}1}\) = Outer boundary of old inner cladding cell, m

\(r_{\text{c}2}\) = Outer boundary of old central cladding cell, m

\(r_{\text{co}}\) = Outer radius of the cladding, m

\(r_{\text{ci}}\) = Inner radius of the cladding, m

The new inner cladding cell energy is then determined form weighting factors based on the old cell radii

(8.4‑15)

\[E_{\text{c,a}} = \frac{\left\lbrack E_{\text{c}} \left( T_{\text{ci}} \right) \cdot W_{1} + E_{\text{c}} \left( T_{\text{cc}} \right) \cdot W_{2} \right\rbrack}{\left\lbrack W_{1} + W_{2} \right\rbrack}\]

where

\(E_{\text{c,a}}\) = Average energy content of the new inner cladding node, J/kg

\(\left( E_{\text{c}} T \right)\) = Cladding energy as a function of temperature, J/kg

\(T_{\text{ci}}\) = Inner temperature of the cladding, K

\(T_{\text{cc}}\) = Central temperature of the cladding, K

\(W = r_{\text{c}1}^{2} - r_{\text{ci}}^{2}\)

\(W_{2} = r_{\text{c}2}^{2} - r_{\text{c}1}^{2}\)

The temperature of the new inner cladding node is then determined.

(8.4‑16)

\[T_{\text{c}1} = T_{\text{c}} \left( E_{\text{c,a}} \right)\]

where

\(T_{\text{c}1}\) = Temperature of modified inner cladding node, K

\(T_{\text{c}} \left( E \right)\) = Cladding temperature as a function of energy, K

The ultimate tensile strength is then determined on the basis of the new node structure.

(8.4‑17)

\[U_{\text{ts}} = \frac{\left\lbrack 3 U_{\text{t}} \left( T_{\text{c}1} \right) + U_{\text{t}} \left( T_{\text{co}} \right) \right\rbrack}{4}\]

where

\(U_{\text{ts}}\) = Average ultimate tensile strength of the cladding, Pa

\(U_{\text{t}} \left( T \right)\) = Ultimate tensile strength as a function of temperature, Pa

\(T_{\text{co}}\) = Cladding outer surface temperature, K

This is the value that determines if failure occurs. If the calculated circumferential stress exclude \(U_{\text{ts}}\), failure is assumed to occur.

The calculated stress is determined in two ways, depending on the relationship between the melt boundary and cracked region of the fuel. If a solid annulus of fuel exists between the melted and cracked regions, the calculated fuel-cladding interface pressure is used

(8.4‑18)

\[\sigma_{\text{c}} = \frac{\left\lbrack P_{\text{fci}} r_{\text{ci}} - P_{\text{ext}} r_{\text{co}} \right\rbrack}{\left\lbrack r_{\text{co}} - r_{\text{ci}} \right\rbrack}\]

where

\(\sigma_{\text{c}}\) = Calculated circumferential stress based on a force balance, Pa

\(P_{\text{fci}}\) = Pressure that exists at the fuel-cladding interface, Pa

\(P_{\text{ext}}\) = Pressure that exists on the outer cladding surface,

If the melting has proceeded to the cracked boundary, then the cladding stress is determined from a force balance on the cladding assuming an inverse \(r\) drop-off in pressure through the solid, cracked fuel.

(8.4‑19)

\[\sigma_{\text{c}} = \frac{\left\lbrack P_{\text{cav}} r_{\text{cav}} - P_{\text{ext}} r_{\text{co}} \right\rbrack}{\left\lbrack r_{\text{co}} - r_{\text{ci}} \right\rbrack}\]

where

\(P_{\text{cav}}\) = Central molten cavity pressure, PA

\(r_{\text{cav}}\) = Radius of the central molten region, m

The failure fraction is then calculated from the cladding stress and ultimate tensile strength.

(8.4‑20)

\[F_{\text{f}} = \frac{\sigma_{\text{c}}}{U_{\text{ts}}}\]

where

\(F_{\text{f}}\) = Cladding failure fraction at current time

When this fraction reaches 1, failure of the cladding at the axial segment is assume to occur. However, this does not mean the ejection of fuel into the coolant channel will take place. Besides cladding failure, the molten fuel radius must have reached the cracked fuel radius. Therefore, there are tow conditions to satisfy prior to initiation of the post failure fuel motion modeling; (1) cladding failure, and (2) complete solid fuel cracking.

Once the post failure fuel motion modeling has been initiated, DEFORM is not used. Control is transferred to PLUTO2 or LEVITATE and the same procedure given above is employed by these modules to determine if the cladding failure propagates to other axial segments.

8.4.5. Time-step Control on Approach to Failure

As the conditions necessary for the failure are approached, the maximum time step is reduced to specified levels. This is controlled through the input parameters FIRLIM, SECLIM, and THRLIM, and the associated time steps DTFALl, DTFAL2, and DTFAL3. When the failure fraction reaches FIRLIM, the main time step will be reduced to DTFAL1 or the current time step, whichever is smaller. This same procedure continues through SECLIM and THRLIM. If

(8.4‑21)

\[0 \leq F_{\text{f}} < \text{FIRLIM}\]

where

\(F_{\text{f}}\) = Failure fraction for the failure condition being used

then the maximum allowable time step is that defined by the initial transient time‑step input parameter DT0.

(8.4‑22)

\[\Delta t = \text{DT}0\]

where

\(\Delta t_{\text{m}}\) = Maximum allowable time-step length, s

If

(8.4‑23)

\[\text{FIRLM} \leq F_{\text{f}} < \text{SECLIM}\]

then

(8.4‑24)

\[\Delta t_{\text{m}} = \text{DTFAL}1\]

Similarly, if

(8.4‑25)

\[\text{SECLIM} \leq F_{\text{f}} < \text{THRLIM}\]

then

(8.4‑26)

\[\Delta t_{\text{m}} = \text{DTFAL}2\]

or, if

(8.4‑27)

\[\text{THRLM} \leq F_{\text{f}} \leq 1\]

then

(8.4‑28)

\[\Delta t_{\text{m}} = \text{DTFAL}3\]

This procedure serves two functions. First, the reduction in main time step produces a corresponding reduction in the PRIMAR time step, thereby allowing the loop model to continue a stable calculation on the initiation of pin failure.Second, the reduced time step on initiation of failure avoids excessive fuel motion in PLUTO2 and LEVITATE prior to the time these failed pin models can initiate their own time‑step control procedures.