Sensitivity calculations

Serpent relies on the collision history based first order GPT equivalent implementation to calculate sensitivities of various responses to various perturbations. As a simple example, the sensitivity of the effective multiplication factor to the different nuclear cross sections can be calculated.

Input

Adding a response

Basic responses

Basic responses can be set up with the syntax

sens resp NAME FLAG

Where the different response names and flags are as follows

NAME	explanation of NAME	FLAG	explanation of FLAG
keff	sensitivity of effective multiplication factor to perturbation	0/1	OFF/ON
beff	sensitivity of effective delayed neutron fraction to perturbation	0/1	OFF/ON
leff	sensitivity of effective prompt generation time to perturbation	0/1	OFF/ON

Omitting (or forgetting) the flag from the definition, will turn the response on by default.

Reaction rate ratios

Sensitivities of reaction rate ratios to perturbations can be set up to be calculated with

sens resp detratio NAME DET1 DET2

Where the paramters are:

NAME	: the name of the response. Will be used in output.
DET1	: Name of the numerator detector, i.e. the one whose reaction rate is being divided.
DET2	: Name of the denominator detector, i.e. the one whose reaction rate is the dividing value.

The two detectors have to be set up separately in normal Serpent fashion.

Notes:

• Currently, each detector can have only one bin.
• Currently, only the indirect effect of the perturbation is calculated and the direct effect must be calculated separately and added to the result.

Adding a perturbation

sens pert NAME FLAG

Where the different perturbation names and flags are as follows

NAME	explanation of NAME	FLAG	explanation of FLAG
xs	perturbation of basic cross sections	0/all/allmt	OFF/sum reaction modes/partial (MT) reaction modes
chi	perturbation of fission spectrum	0/1	OFF/ON
nubar	perturbation of fission nubar	0/1	OFF/ON
eleg	perturbation of Legendre moments of elastic scattering angular distribution	0/1/2/3/4/5/6/7	Number of Legendre moments to perturb.

Omitting (or forgetting) the flag from the definition will turn the perturbation on by default. The default number of Legendre moments to include is 3.

Choosing nuclides to perturb

The perturbed nuclides can be specified by giving a list of the ZAI-numbers to include

sens pert zailist ZAI1 ZAI2 ... 

for example

sens pert zailist 922350 922380

for perturbations affecting ²³⁵U and ²³⁸U. By giving the control words total and/or sum in the list of ZAI-numbers, the total sensitivity over all ZAIs present in the calculation and the sum sensitivity of the listed ZAIs will be calculated, respectively.

All nuclides present in the calculation can be included with

sens pert zailist all

this will automatically include the calculation of the total sensitivity.

Choosing materials to perturb

The materials, where the perturbations are applied can similarly be specified by giving a list of the material names

sens pert matlist MAT1 MAT2 ...

for example

sens pert matlist fuel coolant

for perturbations affecting interactions in materials fuel and coolant. By giving the control words total and/or sum in the list of material names, the total sensitivity over all materials present in the calculation and the sum sensitivity of the listed materials will be calculated, respectively.

All materials present in the calculation can be included with

sens pert matlist all

this will automatically include the calculation of the total sensitivity.

Additional options

The options for sensitivity calculations can be set using the

sens opt ...

syntax.

Energy grid for scoring

The energy grid used for scoring the sensitivities can be set using

sens opt egrid ENAME

where ENAME is a name of an energy grid definition.

Number of latent generations

The number of latent generations used for k-effective sensitivity calculations can be set with

sens opt latgen NGEN

where NGEN is the number of generations to use. The number of summation generations for reaction rate ratios and bilinear-ratios will be NGEN+1

Direct scoring instead of event based scoring

There are two ways to go about calculating the net number of accepted collisions in the collision history of a particle.

1. The default way used by Serpent is to create so-called event-objects during each accepted or rejected event of interest (e.g. collision, sampled fission neutron energy or sampled scattering angle). Then, when the net number of accepted collisions is needed, this list of events is traversed and the net number is calculated. The memory requirement of this method is dependent on the number of interesting events in N_gen generations of particle history, where N_gen is the total number of generations stored for the collision history. In order to save memory, the events are shared by each particle that has the event in their collision history. Traversing through the event tree in order to calculate the net number of a certain event in the collision history can be costly.
2. There is the option to update the net number of a certain event on-the-fly, every time that event is sampled. Event objects are no longer stored. Instead the net number of accepted collisions is either incremented (accepted collision) or decremented (rejected collision) directly. This way each generation in the collision history is associated with a score matrix representing the net number of scores for each of the different events of interest. Again, to save memory each generational score matrix is shared by all neutrons that have that neutron history in their collision history.

In order to use the direct scoring (option 2), the input is

sens opt direct F

Event bank size

The default size of the allocated event bank may be too small for some sensitivity calculations resulting in the following error:

Fatal error in function EventFromBank:

Event bank is empty

Simulation aborted.

The event bank size can be set using

set nbuf NBUF EBANK

where NBUF is the neutron buffer size (default is 5) and EBANK is the event bank size (default is 100).

Output

The output of the sensitivity calculations is written into a MATLAB/OCTAVE readable file [input]_sens.m

General parameters

Parameter	Size	Description
SENS_N_MAT	1	Number of perturbed materials.
SENS_N_ZAI	1	Number of perturbed nuclides (ZAIs).
SENS_N_PERT	1	Number of different perturbation types (cross sections, fission spectra etc.).
SENS_N_ENE	1	Number of energy bins used for tallying the sensitivities.
SENS_MAT_LIST	SENS_N_MAT strings	Array of names for the perturbed materials.
SENS_ZAI_LIST	SENS_N_ZAI	Array of ZAI numbers for the perturbed nuclides.
SENS_PERT_LIST	SENS_N_PERT strings	Array of names for the perturbation types.
SENS_E	SENS_N_ENE + 1	Grid points for the energy grid used for tallying the sensitivities.
SENS_LETHARGY_WIDTHS	SENS_N_ENE	Lethargy widths of the energy bins. Lethargy at the maximum energy bin boundary is 0.

Calculated sensitivities

The calculated sensitivities are printed out both in an energy dependent format (integrated to the energy grid defined by sens opt egrid) and an energy integrated format (integrated over all energies).

The standard sensitivity responses include:

Parameter	Size	Description
ADJ_PERT_KEFF_SENS	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ SENS_N_ENE $\times$ 2	The energy dependent sensitivity of the multiplication factor and the associated statistical error.
ADJ_PERT_KEFF_SENS_E_INT	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ 2	The energy integrated sensitivity of the multiplication factor and the associated statistical error.
ADJ_PERT_BEFF_SENS	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ SENS_N_ENE $\times$ 2	The energy dependent sensitivity of the delayed neutron fraction and the associated statistical error.
ADJ_PERT_BEFF_SENS_E_INT	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ 2	The energy integrated sensitivity of the delayed neutron fraction and the associated statistical error.
ADJ_PERT_LEFF_SENS	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ SENS_N_ENE $\times$ 2	The energy dependent sensitivity of the prompt neutron generation time and the associated statistical error.
ADJ_PERT_LEFF_SENS_E_INT	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ 2	The energy integrated sensitivity of the prompt neutron generation time and the associated statistical error.
ADJ_PERT_VOID_SENS	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ SENS_N_ENE $\times$ 2	The energy dependent sensitivity of the void reactivity coefficient and the associated statistical error.
ADJ_PERT_VOID_SENS_E_INT	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ 2	The energy integrated sensitivity of the void reactivity coefficient and the associated statistical error.

The reaction rate sensitivities defined using sens resp detratio are output as:

Parameter	Size	Description
ADJ_PERT_NAME_SENS	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ SENS_N_ENE $\times$ 2	The energy dependent sensitivity of the reaction rate ratio NAME and the associated statistical error.
ADJ_PERT_NAME_SENS_E_INT	SENS_N_MAT $\times$ SENS_N_ZAI $\times$ SENS_N_PERT $\times$ 2	The energy integrated sensitivity of the reaction rate ratio NAME and the associated statistical error.

Helpful indices

The indices for different materials, ZAIs and perturbations are also included as separate variables of the following format

Parameter	Size	Description
iSENS_MAT_NAME	1	Index corresponding to material NAME.
iSENS_ZAI_NUMBER	1	Index corresponding to the nuclide with ZAI NUMBER.
iSENS_PERT_NAME	1	Index corresponding to the perturbation NAME.

These indices can be used to refer to the different materials, nuclides and perturbations in data processing without the need to manually figure out the indices. For example,

ADJ_PERT_KEFF_SENS(iSENS_MAT_fuel, iSENS_ZAI_922380, iSENS_PERT_CAPT_XS, :, 1)

will refer to the energy dependent sensitivity of the multiplication factor to the perturbation of the capture cross section of uranium 238 in the material fuel.

It should be noted that the indices for certain materials, ZAIs and perturbations only exist if they have been included in the sensitivity calculation using sens pert.

Notes

• The energy dependent sensitivities are integrated over the energy bins and not divided by the bin energy- or lethargy-width.
• The sensitivity output is mostly written as 1D arrays and reshaped and permuted using the appropriate MATLAB/OCTAVE commands (included in the .m file).

Examples

• Flattop k-eff sensitivity example