1 Introduction

In the ECHo experiment, the \(^{163}\)Ho electron capture (EC) spectrum is measured using low temperature metallic magnetic calorimeters (MMCs), with \(^{163}\)Ho enclosed in the absorbers via ion implantation [1]. The biggest effect of a finite electron neutrino mass on the spectrum can be found in the high energy part, just below the maximum energy available for the decay \(Q_{\mathrm {EC}} \simeq 2.8\,\)keV, which corresponds to the mass difference between the parent atom \(^{163}\)Ho and daughter atom \(^{163}\)Dy [2]. The \(^{163}\)Ho spectrum is characterized by several resonances, one for each of the excited states in which the daughter atom can be left and continuous structures related to the emission of X-rays and electrons to the continuum [3, 4] (Fig. 1). Only a small fraction of the order of \(~10^{-9}\) of all decays are located in the region of interest (ROI) of 10 eV below \(Q_{\mathrm {EC}}\). The set-up used for the simulations based on the ECHo-1k design, which consists of an array of 72 MMCs based detector pixels [5]. Accordingly, a count rate of approximately \({8} \cdot 10^{-5}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI.

1.1 Detection mechanism of MMCs

The energy E deposited by a particle in the absorber of a MMC leads to an increase in temperature \(\delta T\) of the MMC:

$$\begin{aligned} \delta T \propto \frac{E}{C}, \end{aligned}$$
(1)

where C is the total heat capacity of the MMC. The increase of the temperature of the paramagnetic sensor results in a change of magnetic moments in the sensor material and thus, in a change of magnetization \(\delta M \propto \delta T\), which is measured with SQUIDS [6].

1.2 Objectives

We consider five background sources: Unresolved pile-up, electromagnetic noise, muons, co-implanted radioactive isotopes and, the topic of this work, naturally occurring radionuclides. In the ECHo experiment, the background level due to naturally occurring radionuclides and due to cosmic radiation (mainly muons and secondary particles produced by muons) has to be reduced in a way that the unresolved pile-up remains the highest background contribution in the ROI.

Preliminary Monte Carlo simulations, performed for the detector set-up of the ECHo-1k experiment [1], provided indicative upper limits on the tolerable concentration of radionuclides in the detector and surrounding materials [7, 8]. Because of the small pixel size of \(180 \times 180 \times 10\,\upmu \)m\(^{3}\), these limits of a few mBq are relatively high and can easily be fulfilled for most of the common radionuclides. In the following, new updated and more detailed Monte Carlo simulations based on screening measurements on some materials used in the ECHo-1k design are discussed in order to determine the expected background contribution due to the identified radionuclides and to give updated upper limits of tolerable concentrations.

In addition, background spectra measured with \(^{163}\)Ho-loaded and non-loaded pixels are studied and compared to the simulations.

Fig. 1
figure 1

Expected \(^{163}\)Ho EC spectrum (blue solid curve) following [3] and related unresolved pile-up spectrum for a pile-up fraction of \(10^{-6}\) (orange solid curve) and considering events with equal and opposite polarity. A Q-value of 2.833 keV and an energy resolution of FWHM = 10 eV are used to calculate the spectra. Inset: The effect of massive neutrinos on the summed spectrum is shown

2 Detector set-up

A simplified design of the ECHo-1k experimental set-up is used in the simulations as shown in Fig. 2. On top of a silicon ECHo-1k chip [9] of dimension 10 mm \(\times \) 5 mm and a thickness of 350 \(\upmu \)m, 36 MMC pairs are placed, resulting in 72 pixels positioned in an array of four lines with 18 pixels each (compare to the insert in Fig. 2). The pixels consist of gold absorbers of dimensions 180 \(\upmu \)m \(\times \) 180 \(\upmu \)m \(\times \) 10 \(\upmu \)m, which are placed directly on top of Ag:Er sensors of dimensions 168 \(\upmu \)m \(\times \) 168 \(\upmu \)m \(\times \) 1.35 \(\upmu \)m [9, 10]. In the middle of the absorbers, thin layers of silver with a thickness of 200 nm and a surface of about 150 \(\upmu \)m \(\times \) 150 \(\upmu \)m are placed as host material for \(^{163}\)Ho. Close to the pixels, relatively large gold structures are positioned (Fig. 2a). Four silicon chips, representing the dc-SQUID chips (Fig. 2b), with dimensions of 6 mm \(\times \) 2.5 mm and thickness of 350 \(\upmu \)m, are positioned close to the ECHo-1k chip (Fig. 2, insert). The circuit boardFootnote 1 (Fig. 2d) covering the copper T-shaped support (called copper holder, Fig. 2c) is modeled as a 0.7 mm thick layer of a bisphenol-based epoxy resins. The copper holder, obtained by a larger annealed oxygen free high conductivity (OFHC) copper piece, has a thickness of 0.7 cm. The T-shape is required in order to have the ECHo-1k chip and SQUID chips at a distance of about 13 cm from the aperture of an aluminum tube used as superconducting shield (Fig. 2f). The circuit board has a gap, so that the five silicon chips can directly be glued on top of a copper holder. A rectangular aluminum tube of 2.5 cm (width) \(\times \) 0.9 cm (height) and a length of 15 cm surrounds the set-up. The wall thickness of the aluminum tube is 3 mm for the bottom and top side and 10.3 mm for the other sides. Last, nine carbon-based connectorsFootnote 2 with a density of 1 g mol\(^{-1}\) are placed at a distance of about 15 cm away from the ECHo-1k chip (Fig. 2e).

Fig. 2
figure 2

Simplified design of the ECHo-1k experiment set-up used in the simulation. Inset: The region close to the ECHo-1k chip. On the purple-colored silicon ECHo-1k chip, 72 MMCs and large thermalization structures (a) are placed. Next to the ECHo-1k chip, four dc-SQUID chips (b) are located. All five silicon-based chips are directly glued on the copper holder (c). A circuit board (d) covers the full copper holder, except the region next to the ECHo-1k chip. Connectors (e) are placed at a distance of about 15 cm from the ECHo-1k chip. An aluminum box (f) surrounds the copper holder

3 Background sources different to natural radionuclides

3.1 Unresolved pile-up

The time profile of the voltage signal caused by the absorption of energy in a MMC is defined by the thermodynamical properties of the detector itself. The shape of the signal can be described by an exponential rise and decay. The rise time \(\tau _\mathrm {r}\) of these pulses, limited by readout bandwidth, is about 500 ns for MMCs in the ECHo-1k phase, while the decay time is a few ms [9]. The rise time defines approximately the time resolution of the detectors i.a., if two decays occurred in the same MMC within a time interval shorter than \(\tau _\mathrm {r}\), they will be interpreted as a single signal with an amplitude corresponding to the sum of the energy released in the two decays. Since each detector channel consists of two pixels, which generate signals of opposite polarity, the unresolved pile-up rate is in first approximation given as twice the product of the activity per pixel A (assuming both pixels having the same \(^{163}\)Ho activity) and the time resolution \(\tau _\mathrm {r}\). Therefore, the count rate is given by \(r_{\mathrm {pu}} = 2 \cdot A^{2} \cdot \tau _{\mathrm {r}}\). In Fig. 1, the continuous blue line represents the expected \(^{163}\)Ho spectrum, following the description in [3] and using a Q-value of 2.833 keV, while the orange line represents the pile-up spectrum. This pile-up spectrum was calculated considering a time resolution of \(\tau _\mathrm {r} = 500\,\)ns and an activity of 1 Bq per pixel, leading to an unresolved pile-up fraction of \(f_\mathrm {pu} = 2 \cdot A \cdot \tau _{\mathrm {r}} = 10^{-6}\). Note that, due to the different polarities of signals generated by the two pixels of the same channel, the total amplitude of a pile-up event can be smaller than the two single signal amplitudes. The pile-up rate in the last 10 eV is about \({{3} \cdot 10^{-6}}\) day\(^{-1}\) pixel\(^{-1}\).

At this point, we would like to note that a more precise shape of the unresolved pile-up spectrum depends on the data reduction algorithm, in particular in relation to pulse shape analysis, which might be more suitable to discriminate pile-up events when the second events have energies above a few hundred eV, as described in [11].

3.2 Electromagnetic noise

Electromagnetic noise can couple to the readout chain of the detectors, resulting in additional background signals. These events can easily be rejected with an efficiency of almost 100 % based on their trigger time information[11].

3.3 Muons

Cosmogenic muons can interact with the MMCs and the material in their surrounding. Thus, muons can deposit energy directly in the MMCs and/or can generate secondary radiation, which can interact with the detector pixels. It was shown that these types of events can either be recognized with the use of an active muon veto, by searching for coincidence among pixels events and by their pulse shape [12]. Out of \(242 \pm 20\) measured pixel-veto coincidences, \(194 \pm 12\) events were also coincidences among pixels, leading to an efficiency of about \((80 \pm 8)\,\%\) of detecting muon induced events by searching for coincidence among pixels.

In addition, by interacting with materials, muons can generate free neutrons, which can activate the materials. In copper, for example, radioactive isotopes of cobalt (like \(^{60}\)Co) or other radionuclides (like \(^{54}\)Mn) can be produced with an accumulated activity concentration of up to the order of mBq kg\(^{-1}\) [13].

3.4 Co-implanted isotopes

In the production process of \(^{163}\)Ho, several other radioistopes, for example \(^{166m}\)Ho [14] or \(^{170}\)Tm/\(^{171}\)Tm [15], are produced. In the ECHo experiment, a two-step separation is used to minimize these byproducts. In particular, a chemical separation is used to ensure that no isotopes different to holmium are left over from the production process [15], followed by mass separation of the holmium fraction at the RISIKO facility [16]. With this, a total \(^{166m}\)Ho/\(^{163}\)Ho ratio below \(5 \cdot 10^{-10}\) is achieved in the MMCs.

4 Natural radionuclides

The region of interest for the ECHo experiment is below 3 keV. Thus, especially low energy radiation, which could be produced directly in or next to the MMCs, has to be investigated. Radionuclides produce mostly low energy particles when decaying via the \(\beta \)-decay or EC decay. But also, Auger electrons and X-rays resulting from the rearrangement of the atomic shell, appearing by nuclear decays also including \(\alpha \)-decays, have a probability to have low energies, below a few keV. In the following, the \({{\beta }}\)-decaying daughters of the \(^{238}\)U-chainFootnote 3 and \(^{232}\)Th-chainFootnote 4 as well as \(^{40}\)K are introduced, which represent the most frequent naturally occurring and relevant nuclides for the ECHo experiment. Only particles with energies less than 20 keV and an emission probability higher than 1 % per decay are listed. The following values are taken from [17] and [18]. The performed simulations include all decay modes, allowing therefore to investigate also low energy particles generated in scattering processes by \(\alpha \)-particles and other energetic particles like \(\gamma \)- and \(\delta \)-radiation.

4.1 \({{}^{{238}}}\)U-chain

\({^{{238}}}\)U can be found in the earth crust with an abundance of about 3 mg per kg [19] and thus, it also occurs in concrete and metals. The most prominent \(\alpha \)-decaying daughter of \(^{238}\)U is the gaseous \(^{222}\)Rn, which can be accumulated in indoor air with concentrations of several tens of Bq per m\(^{3}\) [20]. Further, radon atoms can be accumulated on surfaces and so, the \(^{222}\)Rn daughters can be implanted in the detector materials due to the recoil after the \(\alpha \)-decays. For example, concentrations of \(^{210}\)Pb and \(^{210}\)Po of the order of \(10^{-4}\) mBq cm\(^{-2}\) can be accumulated on the surface of OFHC copper [21].

\(^{{234}}\)Th decays with a Q-value of 274 keV to \(^{234}\)Pa. The half life is 24.1 days. The daughter is always in an excited state of 74 keV (78 %), 166 keV (\(\sim 20\) %) or 187 keV (\(\sim 2\) %). The corresponding mean energy of the electron is about 54 keV (78 %), 28 keV (\(\sim 20\) %) or 22 keV (\(\sim 2\) %) respectively. Protactinium L X-rays of energies between 11 keV and 21 keV and protactinium L Auger electrons with energies between 6 keV and 21 keV occur each in about 8 % of all decays. In addition, a 11 keV conversion electron (CE) from the L-shell can be emitted in about 4 % of all decays.

\(^{{234}}\)Pa decays with a Q-value of 2194 keV to \(^{234}\)U with a half life of 6.7 hours. Many transitions can occur, the \(\beta \)-particles have always relatively large energies (\(> 30\,\)keV) due to the related high Q-value. The probability for emitting uranium L X-rays of energies between 11 keV and 21 keV and uranium L Auger electrons with energies between 6 keV and 21 keV are very high, they are emitted in about 88 % of all decays. Conversion electrons from the K-shell with energies of 16 keV (3.9 %) and 19 keV (1 %) can also be emitted.

\(^{{214}}\)Pb has a Q-value of 1018 keV and a half life of about 27 minutes. With a probability of about 89 %, the daughter nuclide \(^{214}\)Bi can be in four possible excited states of 295 keV (40 %), 352 keV (46 %), 534 keV (1 %) and 839 keV (\(\sim 3\) %). The mean energy of the \(\beta \)-particles corresponding to the decay to the 839 keV state is about 50 keV. Bismuth X-rays with energies between 9 and 16 keV occur in about 12 % and the probability that 5 keV to 16 keV bismuth L Auger electrons occur is about 19 %.

\(^{{214}}\)Bi decays mostly (\(\sim 99.98\) %) to \(^{214}\)Po. The half life of this decay is about 20 minutes with a Q-value of about 3270 keV. After the decay, the daughter nuclide is in the ground state in about 19 % of all decays. As in the case of \(^{234}\)Pa, the energy of the emitted \(\beta \)-particles is large because of the high Q-value. Nearly no low energy particles are expected, only polonium L Auger electrons with energies between 5 keV and 17 keV in about 1 % of all decays.

\(^{{210}}\)Pb has a half life of about 22 years and a Q-value of about 63 keV. In about 84 %, the daughter \(^{210}\)Bi is in an excited state with an energy of 47 keV. With a probability of about 23 %, bismuth X-rays with energies between 9 keV and 16 keV are emitted. Bismuth L Auger electrons with energies between 5 keV and 16 keV occur in about 35 % of all decays.

\(^{{210}}\)Bi has a half life of about 5 days and a Q-value of about 1160 keV. The daughter nuclide is always in the ground sate.

4.2 \(^{{232}}\)Th-chain

\({^{232}}\)Th can be found in the earth crust with an abundance of about 10 mg per kg [19] and hence, \(^{232}\)Th and its daughters also occur in metals. As \({^{238}}\)U, \({^{232}}\)Th has also gaseous daughters, however these and their daughters only have short lifetimes. Thus, these can not be accumulated very well on surfaces after the surface is no more exposed to air.

\({^{228}}\)Ra decays to \(^{228}\)Ac with a half life of about 6 years and a Q-value of about 46 keV. The daughter nuclide can be in excited states of about 6 keV (50 %), 20 keV (20 %) or 33 keV (30 %). This corresponds to small mean energies of the emitted electrons of about 3 keV to 10 keV. Due to the small excitation levels of a few keV, low energy gamma radiation can be emitted. Gamma radiation occurs with a probability of about 3 % with energies in the range of 13 keV to 16 keV. Actinium L X-rays with energies of 11 keV to 20 keV occur in about 1 % of all decays, as well as 6 keV to 20 keV actinium L Auger electrons. In addition, conversion electrons with energies around 2 keV (45 %), 5 keV to 10 keV (29 %) and 11 keV to 26 keV (12 %) are emitted.

\({^{228}}\)Ac further decays to \(^{228}\)Th. The Q-value is about 2124 keV and the half life about 6 hours. Almost in any transition, a relatively high energy electron (\(> 30\,\)keV) is emitted and the daughter nuclide is in an excited state. Compared to the other decays, the probability of about 33 % of 11 to 20 keV thorium L X-rays is quite high, as well as the probability of 6 keV to 20 keV thorium L Auger electrons of about 37 %.

\({^{212}}\)Pb has a half life of about 11 hours and decays with a Q-value of about 574 keV to \(^{212}\)Bi. \(^{212}\)Bi can be in three states: The ground state (\(\sim 12\,\)%), an excited state of an energy of about 239 keV (\(\sim 83\,\)%) or of about 415 keV (\(\sim 5.2\,\)%). 5 keV to 16 keV bismuth L auger electrons are emitted in about 22 % of all decays, while 9 keV to 16 keV bismuth L X-rays occur with a probability of about 14 %.

\({^{212}}\)Bi is special, compared to the other discussed isotopes. The probability of \(\beta ^{-}\)-decay is only about 64 %, while 36 % of the decay are an \(\alpha \)-decay. The half life is about 61 minutes and in case of the \(\beta \)-decay, the Q-value is about 2252 keV. The daughter nuclide \(^{212}\)Po is in the ground state in about 86 % of all \(\beta \)-decays and in an excited state with an energy between 700 keV and 1805 keV in 14 %. X-ray and Auger electrons occur only in case of the \(\alpha \)-decaying branch. The probability for these emissions after a \(\beta \)-decay is less than 0.5 %. Thus, thallium L X-rays with energies of 9 keV to 15 keV are emitted in about 7 % of all decays and thallium L Auger electrons with energies between 5 keV and 15 keV in about 12 %.

\({^{208}}\)Tl decays to \(^{208}\)Pb with a half life of about 3 minutes and a high Q-value of about 5000 keV. After the decay, the daughter nuclide is in one of 15 possible excited states in the range of 3197 keV to 4480 keV. 9 keV to 16 keV lead L X-ray occur in about 3 % and lead L Auger electrons with energies of 5 keV to 16 keV in about 5 %.

4.3 \({^{40}}\)K

\({^{40}}\)K is present in natural potassium with an abundance of 0.0117 % [17]. Its half life is 1.277 Gy and it has two decay branches. It decays to \(^{40}\)Ca via a \(\beta ^{-}\) process (\(\sim 89\) %) and a Q-value of around 1311 keV or to \(^{40}\)Ar via electron capture (EC) decay or \(\beta ^{+}\)-decay (\(\sim 11\) %) and a Q-value of about 1505 keV. While the daughter \(^{40}\)Ca nucleus is always in the ground state, the \(^{40}\)Ar nucleus is always in an excited state of 1461 keV. In case of the EC/\(\beta ^{+}\)-decay, argon K X-ray with energies around 3 keV are emitted with a probability of about 10 %, argon L Auger electrons with energies of about 300 eV with a probability of about 145 %Footnote 5 and argon K Auger electrons with energies between 2.5 keV and 3.2 keV in about 130 %\({^{5}}\) of all EC/\(\beta ^{+}\)-decays.

5 Screening measurement

In order to estimate the influence of naturally occurring radionuclides in the experimental set-up, screening measurements were performed to identify the presence of radionuclides in the materials used for the detector setup, as well as parts of the cryostat. The screening measurements were conducted in the shallow underground laboratories at Tübingen with a shielding against cosmogenic radiation of about 16 m.w.e. [22]. The sensitivity of the used high purity germanium detector [23] on radioactive contamination is mainly limited by the internal contamination of the detector itself. Dominant internal contamination features of the background spectrum correspond to about \(15 \cdot 10^{-4}\) counts s\(^{-1}\) of the \(^{40}\)K 1460 keV line, \(12 \cdot 10^{-4}\) and \(18 \cdot 10^{-4}\) counts s\(^{-1}\) for the \(^{208}\)Tl 2615 keV and 583 keV lines respectively and \(30 \cdot 10^{-4}\) counts s\(^{-1}\) of the 239 keV \(^{212}\)Pb line. If no larger rates would be measured for the tested samples, an upper limit, the 95 % C.L., is calculated by using the internal limitations.

The screened samples are 50 g of cryostat copper used as high thermal conductivity holder for the detector set-up indicated with (c) in Fig. 2, a batch of 15 connectors ((e) in Fig. 2) with a total weight of 7.5 g and a printed circuit board with a weight of 13.63 g ((d) in Fig. 2). The results of the screening measurement are shown in Table 1 for bulk contaminations and in Table 2 for surface contaminations. The latter are calculated by comparing the screening measurement with simulations of \(^{40}\)K located one monolayer (\(10^{-10}\) m) below the surface and \(^{210}\)Pb, which is implanted in the material by the recoil of the decay of \(^{222}\)Rn and its daughters. The typical measurement duration for these screening and background measurements was approximately a month each.

Table 1 Results of the screening measurement
Table 2 Results of the screening measurement

Typical concentration of contamination in pure metals are in the order of 0.1 mBq kg\(^{-1}\) to 1 mBq kg\(^{-1}\) [24, 25] and concentrations about 1 Bq kg\(^{-1}\) to 2 Bq kg\(^{-1}\) in non pure metals and alloys [26], mainly due to the \(^{232}\)Th and \(^{238}\)U chains. So, it is expected that for pure metals like the copper samples, only upper limits can be given. Concentrations of the order of \(10^{-4}\) mBq cm\(^{-2}\) [21] or of 17 mBq kg\(^{-1}\) to 40 mBq kg\(^{-1}\)[27] are expected for \(^{210}\)Pb in the copper sample and concentrations of the order of \(10^{-3}\) mBq kg\(^{-1}\) for \(^{232}\)Th and \(^{238}\)U [28]. However, this is far below the sensitivity of the used detector. Smaller limits for the copper sample are given by a screening measurement including a similar copper sample with a mass of about 500 g, performed by the team of the Canfranc Underground Laboratory results in upper limits of about 40 mBq kg\(^{-1}\) for the \(^{232}\)Th-chain,Footnote 6 about 120 mBq kg\(^{-1}\) for the \(^{238}\)U-chain\(^{7}\) and 25 mBq kg\(^{-1}\) of \(^{40}\)K [29]. By comparing to the limits resulting from the screening measurement of the copper sample in Tübingen and assuming similar relations between the limits of \(^{40}\)K surface to bulk contamination and \(^{238}\)U bulk contamination to \(^{210}\)Pb surface contamination, these limits leads to surface contaminations of less than 25 \({\upmu }\)Bq cm\(^{-2}\) for \(^{40}\)K and 28 \({\upmu }\)Bq cm\(^{-2}\) for the \(^{210}\)Pb-chain. Similar levels of contamination are also expected for pure aluminum samples [28].

The higher values for plastic (connectors) and the colored circuit board are as well expected. Crude oil and coal are often basic materials for plastics, binders (plastic dispersions) and solvent. Both, crude oil and coal are known to have relatively large levels of concentrations of natural occurring radionuclides of about tens to hundreds of Bq kg\(^{-1}\) [30,31,32]. In newer MMC set-up for low background measurement, polyimide based circuit boards (Kapton) are used due to the very low concentration levels of natural radionuclides [29].

6 Monte Carlo simulation

The decays of the radionuclides are simulated using version 10.06.p03 of the GEANT4 toolkit [33]. To study accurately the effect of natural radionuclides located in the surrounding of the MMCs and to decrease computation time as much as possible, the predefined particle production energy thresholds are configured. If a potentially produced particle by a process with infrared divergence, such as bremsstrahlung or \(\delta \)-ray production, the particle will only be generated, if its kinetic energy is above a given energy threshold. If the kinetic energy of the potentially produced particles is below the energy threshold, their kinetic energy is deposited locally. Particles generated by other processes like the radioactive decay or atomic de-excitation are not affected by this cut.

6.1 Simulation set-up

In order to produce as many low energy particles as possible in the close surrounding of the MMCs, the energy threshold is reduced layer by layer. The discussed energy threshold is equivalent to a minimum distance the particles have to pass before getting absorbed. These minimum ranges are shown in Table 3 for different volumes. The larger volumes like the copper holder, aluminum shielding and the substrate of the ECHo-1k chip contain sub volumes as seen in Fig. 3, showing the profile of the set-up around the ECHo-1k chip.

Table 3 The minimum ranges particles have to pass for different volumes
Fig. 3
figure 3

Non-scaled scheme of the region around the ECHo-1k chip. The minimum ranges particles have to pass before getting absorbed in different layers of the larger volumes and their dimensions are shown. Picture taken from [12]

The simulations are divided into two sets. If the radionuclides are uniformly distributed in the volume materials, they are called bulk-distributed and if the radionuclides are located only on the surface of the volumes,Footnote 7 they are called surface-distributed. The full decay chains of the nuclides are simulated. The large number of simulated events of the order of \(10^{6}\) to \(10^{8}\) for each nuclide are needed to obtain high statistics describing the deposited energies of less than 6 keV in the MMC pixels to study the shape of the spectrum in this region. For levels of radioactivity as high as resulting from the screening measurement, the number of simulated decays corresponds to very long measuring times of the order of a few thousand days (compare to Tables 4 and 5). Since no screening measurements are available for the detector-pixels and the aluminum shielding until now, the upper limits of concentrations of the copper sample (from the measurement in the Canfranc Underground Laboratory) is used for the detector pixels, the shielding and copper holder. The two copper samples screened in Tübingen and Canfranc have different shapes. Nevertheless, the same ratio between bulk and surface contamination resulting from the measurement in Tübingen is also assumed for the copper sample used in Canfranc. In order to safe computation time, radionuclides are only placed at the first quarter (next to ECHo-1k chip) of the circuit board. Naturally occurring radionuclides in the connectors are not simulated. For comparison, the simulation of \(28 \cdot 10^{6}\) decays of \(^{238}\)U and its daughters in the bulk of the part of the circuit board next to the ECHo-1k chip results in 846 particles hitting the MMCs, while the simulation of \(3 \cdot 10^{6}\) decays of \(^{238}\)U and its daughters in the bulk of the rest of the circuit board results only in two hits. Thus, by considering only events due to radionuclides in the circuit board, it can be assumed, that about 94 % of all particles hitting the detector pixels, are produced by particles created in the part of the circuit board, which is next to the detector pixels. The connectors are relatively far away from the active volume and the aluminum shielding is between the connectors and the active volume (except of the middle connector). They have similar levels of contamination as the circuit board, but result in a smaller solid angle coverage with respect to the active volume. Thus, radionuclides in the connectors should have less influence on the background, by comparing to radionulcides in the circuit board. Radionuclides in the substrate are also not simulated yet, because metallic contamination of less than \(10^{11}\) atoms cm\(^{-3}\) can easily be achieved [34, 35], which is equal to an activity of less than 10 \(\upmu \)Bq kg\(^{-1}\).

Table 4 Number of simulated bulk-distributed decay chains
Table 5 Number of simulated surface-distributed decay chains

Following, the values of expected count rates in the last 10 eV below \(Q_{\mathrm {EC}}\) are determined by fitting an exponential decay to the spectra in the 1 keV to 5 keV range and averaging of the 2.6 keV to 3 keV range. The obtained value is further scaled with the (upper limit) activity resulting from the screening measurement.

Fig. 4
figure 4

Simulated spectrum of deposited energies in the MMC absorbers caused by the bulk-distributed \(^{238}\)U-chain. The fractions due to the single nuclides of this chain are colored. The summed spectrum is structure-less for low energies. Nuclides decaying by an \(\alpha \)-decay change the spectrum only minor at low energies, exemplary shown for \(^{238}\)U. However, \(\alpha \)-particles can escape the absorber and hit the aluminum shielding or the substrate. Thus, aluminum K X-ray and Auger electrons and silicon (substrate) K X-ray and Auger electrons as well as \(\delta \)-ray generated by \(\alpha \)-particles can hit the absorbers

Fig. 5
figure 5

Simulated spectrum of deposited energies in the MMC absorbers caused by the surface-distributed \(^{238}\)U-chain on the absorbers. The fractions due to the single nuclides of this chain are colored. The \(\alpha \)-particles can be emitted by any isotope. For low energies, the summed spectrum has no structures. Nuclides decaying by an \(\alpha \)-decay change the spectrum only minor at low energies. At higher energies however, these nuclides provide many features

6.2 Radionuclides in single pixels

6.2.1 \({^{238}}\)U-chain

The energy deposition caused by bulk-distributed radionuclides of the \(^{238}\)U-chain in the absorbers of the MMCs is shown in Fig. 4. The colors indicate the fractions of the summed spectra caused by the nuclides of the decay chain. The \(\alpha \)-decaying isotopes have only a minor effect on the spectrum in the energy region below 6 keV and are not shown, except of \(^{238}\)U. However, the emitted \(\alpha \)-particles can leave the absorbers and hit the material surrounding the MMC array. Thus, structures at 1.5 keV and 1.7 keV can be identified, which corresponds to aluminum and silicon K-shell X-rays and Auger electrons generated in the aluminum shielding and the substrate. In addition, \(\delta \)-ray produced by \(\alpha \)-particles can deposit energy in the absorbers. Events caused by \(\alpha \)-particles, hitting the surrounding, should show coincidences among pixels, meaning that in one pixel energy is deposited by products of the \(\alpha \)-decay. Another pixel is hit by X-ray, Auger electrons and/or \(\delta \)-ray generated by the \(\alpha \)-particle in the surrounding. At higher energies, structures like the 47 keV \(^{210}\)Pb edge, the peak at 73.9 keV due to the decay of the metastable J\(^{\mathrm {P}}\) state of \(^{234}\)Pa and exemplary the edge around 72 keV caused by \(^{238}\)U, are visible. By assuming an equilibrium of the members of the \(^{238}\)U-chain and accumulated activity level of 0.12 Bq kg\(^{-1}\), which is equal to about \(7 \cdot 10^{8}\) atoms of the \(^{238}\)U-chain in each MMC or \(10^{-8}\) of the absorber material, a signal count rate of about \((3.8 \pm 0.1) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI.

Fig. 6
figure 6

Simulated spectrum of deposited energies in the MMC absorbers caused by the bulk-distributed \(^{232}\)Th-chain as in the absorbers. The fractions due to the single nuclides of this chain are colored. The \(\alpha \)-particles can be emitted by any isotope. No special structures can be observed for low energies. At higher energies, the \(^{228}\)Ra gamma levels at 6.5 keV, 20 keV and 33 keV can be identified, as well as the 58 keV level of the decay of\(^{228}\)Ac

Fig. 7
figure 7

Simulated spectrum of deposited energies in the MMC absorbers caused by the bulk-distributed \(^{40}\)K in the absorbers. The \(\beta \)-spectrum is flat for low energies and the Ar shell levels due to the EC/\(\beta ^{+}\)-decay can be seen

Fig. 8
figure 8

Simulated spectrum of deposited energies in the MMC absorbers caused by the surface-distributed \(^{40}\)K on the absorbers. The Ar lines are visible. But, in comparison to bulk contamination, they are broader, because not all X-ray and Auger electrons have to be emitted to the absorber

Figure 5 shows the spectrum caused by surface-distributed \(^{238}\)U on the surface of an absorber. As in the case of bulk-distribution, the summed spectrum has no structures at low energies and the \(\alpha \)-decaying isotopes have only a minor effect on the spectrum below 6 keV. On the other hand, many features can be observed at higher energies. These occur, because not all decay products deposit their energy in the absorber. The peaks due to the \(\alpha \)-decaying isotopes are visible at energies of their Q-value reduced by the energy of the emitted \(\alpha \) particles, which is the recoil energy of the daughter nucleus. For example \(^{238}\)U: \(4270\,\)keV\(\,-\,4198\,\)keV\(\,=72\,\)keV. More than one peak is visible at these energies, because the energy released in de-excitation process of gold atoms (excited during the nuclear recoil) emitted either as Auger electrons or X-rays, which can escape the absorber. For surface-distribution, the 186 keV gamma of \(^{226}\)Ra has a higher path length in the absorbers compared to bulk-distribution and so, has a higher probability to ionize. Thus, the 68 keV KL X-ray line of gold is visible. \(^{234}\)Th provides many features, the 29 keV, 63 keV, 74 keV and 92 keV gamma levels as well as the corresponding X-ray escape peaks. Note that not only gold X-ray can escape, but also X-ray emitted by the daughter nuclides. From \(^{234}\)Pa, the 43 keV gamma level and from \(^{214}\)Pb, excited during the \(\alpha \)-decay, the 53 keV level can be identified. Also, at energies above 80 keV, \(\alpha \)-particles generate more structures. Due to the recoil of the nucleus, the daughter nuclide of an \(\alpha \)-decaying nuclide can leave the absorber. Thus, there is a chance that only the \(\alpha \)-particle emitted by these daughters can deposit energy in the absorbers. Only \(^{210}\)Pb and its daughters \(^{210}\)Bi and \(^{210}\)Po should be surface-distributed due to accumulated \(^{222}\)Rn.Footnote 8

With an activity concentration of 0.028 mBq cm\(^{-2}\), a count rate of about \((1.9 \pm 0.1) \cdot 10^{-8}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI from these radionuclides, which only corresponds to about 200 atoms on each MMC surface.

6.2.2 \(^{232}\)Th-chain

The effect of bulk-distributed \(^{232}\)Th is shown in Fig. 6. As in the case of bulk-distributed \(^{238}\)U, \(\alpha \)-decaying isotopes have only a negligible effect on the spectrum at low energies. The summed spectra has no structures in the low energy region, but a few features can be identified at higher energies. The three \(^{228}\)Ra edges at around 6.5 keV, 20 keV and 33 keV can be seen. Also, the 58 keV excitation level of \(^{228}\)Th, the daughter of \(^{228}\)Ac is visible as well as exemplary the edge of \(^{232}\)Th. In case of \(^{228}\)Ra, there is a chance that \(^{228}\)Ac with a half life of about 6 hours decays simultaneously (the time interval used in the simulation to generate pile-up events is \(\delta t < 1\,\)ms) and thus, higher energies than the Q-value of \(^{228}\)Ra of about 46 keV can be measured. For an activity concentration of 0.04 Bq kg\(^{-1}\) (about \(10^{9}\) atoms per MMC or \(10^{-8}\) of the absorber material), a count rate of about \((4.5 \pm 0.1) \cdot 10^{-10}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI.

6.2.3 \({^{40}}\)K

The resulting simulated spectrum of bulk-distributed \(^{40}\)K in an absorber can be seen in Fig. 7. The only visible features are the Ar shell levels due to the EC/\(\beta ^{+}\)-decay at 0.3 keV and 3.2 keV. The \(\beta \)-spectrum is flat for energies below 6 keV.

For an activity concentration of 0.025 Bq kg\(^{-1}\) (about \(10^{8}\) atoms per MMC or \(7 \cdot 10^{-9}\) of the absorber material), a count rate of about \((3.2 \pm 0.1) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the last 10 eV below \(Q_{\mathrm {EC}}\). Figure 8 shows the spectrum caused by surface-distributed \(^{40}\)K on the surface of an absorber. Compared to bulk-distributed \(^{40}\)K, the lines due to the EC/\(\beta ^{+}\)-decay are broader. This happens, because not all Auger electrons and X-ray deposit all their energy in the absorber. For an activity concentration of 0.025 mBq cm\(^{-2}\) (about \(3 \cdot 10^{10}\) atoms per MMC-surface or 0.5 % of the surface atoms), a count rate of about \((2 \pm 1) \cdot 10^{-7}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI.

6.3 Radionuclides in the aluminum shielding

6.3.1 \({^{238}}\)U-chain

The resulting simulated spectra for bulk- and surface-distributed \(^{238}\)U in the aluminum shielding can be seen in Figs. 9 and 10 respectively. In case of bulk-distribution, mainly higher energy electrons/\(\beta \)-particles deposit energy in the absorbers and thus, mainly the \(\beta \)-decaying isotopes with higher Q-values (\(\ge 1\,\)MeV) are listed, but also the excited daughters of \(^{214}\)Po can often emit high energy conversion electrons. The \(\alpha \)-particles can generate much \(\delta \)-radiation, which can deposit energy in the absorbers. Mainly the Landau distribution [36] caused by these electrons can be seen. For comparison, the Landau distribution caused by 500 keV electrons passing the absorbers is plotted. Similar to the surface-distribution of \(^{238}\)U on the absorbers, the spectrum resulting from surface-distributed \(^{238}\)U in the shielding shows peaks from \(\alpha \)-decaying isotopes, which can be seen at energies at the Q-values minus the energy of the emitted \(\alpha \)-particle. Also, the \(\alpha \)-particles can produce \(\delta \)-radiation and X-ray, which results in deposited energies lower than 6 keV. An activity concentration of bulk-distributed \(^{238}\)U of 0.12 Bq kg\(^{-1}\) results in a count rate of less than \(2.7 \cdot 10^{-8}\) day\(^{-1}\) pixel\(^{-1}\) at \(90\,\%\) C.L. in the ROI and surface-distributed \(^{210}\)Pb and daughters with a level of 0.028 mBq cm\(^{-2}\) result in a count rate of about \((6 \pm 1) \cdot 10^{-8}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI.

Fig. 9
figure 9

Simulated spectrum of deposited energies in the MMC absorbers caused by the bulk-distributed \(^{238}\)U-chain in the aluminum shielding. No special structures are observable. Mainly, electrons (\(\beta \)-particles) deposit energy in the absorbers. A Landau distribution [36] is expected to be caused by these electrons and can be compared to a Landau distribution for 500 keV electrons passing the absorbers [37]

Fig. 10
figure 10

Simulated spectrum of deposited energies in the MMC absorbers caused by the surface-distributed \(^{238}\)U on the aluminum shielding. Lines caused by the \(\alpha \)-decaying isotopes can be identified. Also, low energy particles generated by \(\alpha \)-particles in the surrounding of the MMCs can hit the pixels

6.3.2 \({^{232}}\)Th-chain

\(^{232}\)Th in and on the aluminum shielding results in the same structures like the ones resulting from \(^{238}\)U in the shielding, the Landau distribution caused by electrons. Bulk-distributed \(^{232}\)Th with a level of 0.04 Bq kg\(^{-1}\) results in a count rate of \((6 \pm 2) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI.

6.3.3 \({^{40}}\)K

The spectra resulting from \(^{40}\)K show no structures. Bulk-distributed \(^{40}\)K with a level of 0.025 Bq kg\(^{-1}\) results in a count rate of \((8 \pm 3) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI and results surface-distributed and with a level of 0.025 mBq cm\(^{-2}\) in a count rate of about \((4 \pm 2) \cdot 10^{-7}\) day\(^{-1}\)  pixel\(^{-1}\) in the ROI.

6.4 Radionuclides in the copper holder

Naturally occurring radionuclides located in the copper holder results in similar spectra as resulting from radionuclides in the aluminum shielding, but with lower intensities. With the same concentrations as used for the absorbers and shielding, nuclides of the \(^{238}\)U-chain cause a count rate of \((6 \pm 1) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI for bulk-distributed nuclides and \((6 \pm 2) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) for surface-distributed \(^{210}\)Pb. For bulk-distributed \(^{232}\)Th, a count rate of about \((2 \pm 1) \cdot 10^{-9}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI is expected. Bulk-distributed \(^{40}\)K results in a count rate of less than \(8 \cdot 10^{-9}\) counts day\(^{-1}\) pixel\(^{-1}\) in the ROI at \(90\,\%\) C.L. and in about \((1.7 \pm 0.3) \cdot 10^{-8}\) day\(^{-1}\) pixel\(^{-1}\), if surface-distributed.

6.5 Radionuclides in the circuit board

Bulk-distributed \(^{238}\)U, with a level of 88 Bq kg\(^{-1}\) in the circuit board, results in a count rate of about \((1.4 \pm 0.4) \cdot 10^{-6}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI and in \((1.6 \pm 0.3) \cdot 10^{-6}\) day\(^{-1}\) pixel\(^{-1}\) for the surface-distributed \(^{210}\)Pb-chain with a level of 2.51 mBq cm\(^{-2}\). The spectra of energy deposited in the MMCs caused by the \(^{238}\)U-chain in the circuit board is shown in Fig. 11 and are similar to the ones caused by \(^{238}\)U and its daughters in the aluminum shielding. For bulk-distributed \(^{232}\)Th with a level of 128 Bq kg\(^{-1}\), a count rate of about \((2 \pm 1) \cdot 10^{-6}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI. Bulk-distributed \(^{40}\)K with a level of 6.2 Bq kg\(^{-1}\) results in about \((3 \pm 1) \cdot 10^{-7}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI and in about \((5 \pm 2) \cdot 10^{-7}\) day\(^{-1}\) pixel\(^{-1}\), if surface-distributed with a level of 0.53 mBq cm\(^{-2}\).

Fig. 11
figure 11

Simulated spectrum of deposited energies in the MMC absorbers caused by a bulk-distributed \(^{238}\)U and b surface-distributed \(^{238}\)U in the circuit bard

6.6 Upper limits

Upper limits of tolerable concentrations of naturally occurring radionuclides are obtained by fitting an exponential distribution to the spectra and scaled, so that the count rate in the last 10 eV below the Q-value of the \(^{163}\)Ho EC is equal to the expected rate of unresolved pile-up of about \({10^{-6}}\) day\(^{-1}\) pixel\(^{-1}\). The resulting concentration limits for bulk- and surface-distributed radionuclides are listed in Tables 6 and 7.

Compared to the results of the screening measurement of Chapter 5, the upper limits of tolerable concentrations are much larger than the upper limits determined in the screening campaign, except of the limits for the circuit board. By assuming that \(^{40}\)K is only surface-distributed, a total count rate of \({\left( 6 \pm 1 \right) \cdot 10^{-6}}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI, mainly due to radionuclides in the circuit board (about 87 %), which is in the same order than the unresolved pile-up. The expected background spectrum is shown in Fig. 12. In future stages of the ECHo experiment, the circuit board will be made of polyimide-based materials, resulting in lower concentrations of radionuclides. However, the background level of the order of \(10^{-6}\) day\(^{-1}\) pixel\(^{-1}\) does not danger the ECHo-1k phase, since this background results in a count rate of about \(10^{-5}\) day\(^{-1}\) pixel\(^{-1}\) in the energy range of \(Q_{\mathrm {EC}} \pm 100\) eV and thus, only one background event is expected with an exposure of five month and 64 pixels.

Table 6 Necessary activity concentrations in Bq kg\(^{-1}\) for a count rate due to radionuclides equal to the unresolved pile-up count rate in the ROI
Table 7 Necessary activity concentration in mBq cm\(^{-2}\) for a count rate due to radionuclides equal to the unresolved pile-up count rate in the ROI
Fig. 12
figure 12

Total expected spectrum of deposited energies caused by natural occurring radionuclides in materials next to the detector arrays. The only visible structure is caused by 1.486 keV aluminum X-rays

7 Background measurement

Due do the double-meander pick-up coil geometry of the MMCs, two pixels are readout by the same SQUID. In the following, these pairs of pixels are called channels. The ECHo-1k high statistics spectrum has been acquired in two independent runs between Dec 2019 and May 2020. In both runs, several channels of two ECHo-1k chips have been used. A description of the detectors used for this ECHo-1k measurement can be found in [9]. Here, we describe the analysis of events acquired in five asymmetric channels, meaning channels in which only one pixel was implanted with \(^{163}\)Ho. The pixels without \(^{163}\)Ho can therefore be used for background measurements. In total, about 241 pixel-days of data of pure background have been analyzed.

The thermodynamical properties of the two pixels of one channel are nearly identical. In order to separate events caused by particles, which deposit their complete energies in the pixels from events caused by particles, which are not fully stopped in the pixels, signals due to the decay of \(^{163}\)Ho of the implanted pixels are analyzed first. The signal pulse shape can be described by several parameters and are calibrated by using \(^{163}\)Ho events, which correspond to events due to particles fully stopped in the pixels. This calibration, as well as the energy calibration, are adapted for the analysis of events in the background pixels.

The pulse shape analysis is based on the analysis developed to recognize muon induced events [12, 38] and modified to select \(^{163}\)Ho-like events. Five parameters are obtained from each pulse, its integral, rise time and amplitude on the one hand, and on the other hand, the pulse is compared to a template and is correlated with the same template. Events, caused by particles depositing their complete energy in the pixels, are identified by comparing these parameters to each other.

7.1 Background estimation

Events with energies above 3 keV are chosen from the data set containing data of the five \(^{163}\)Ho-loaded pixels. Above 3 keV, only unresolved pile-up events and background events are expected, while above 6 keV only background events are expected. However, due to ADC settings the pulse height is limited to about 5 keV. We measured four events with energies between 3 keV and 5 keV in 241 pixel-days after pulse shape analysis. In the same energy region, we expect about 0.7 counts due to unresolved pile-up events. However, by considering the pile-up spectrum, the probability that one count of these events is caused by pile-up is about 22 % and less then 0.2 % that more then one of these counts are caused by pile-up. The expected pile-up spectrum normalized to the 3 keV to 5 keV energy region and the measured events are shown in Fig. 13. Thus, these events are more likely caused by a different background source. Assuming a flat background level, this results in a background level of \((8 \pm 4) \cdot 10^{-5}\) pixel\(^{-1}\) day\(^{-1}\) in the last 10 eV before \(Q_{\mathrm {EC}}\), which is higher than the estimated background due to radionuclides of \(6 \cdot 10^{-6}\) pixel\(^{-1}\) day\(^{-1}\).

Fig. 13
figure 13

Normalized energy spectra of unresolved pile-up and measured events in 241 pixel-days

The energy spectrum recorded by the background pixels, which are not loaded with \(^{163}\)Ho, is shown in Fig. 14. After the pulse shape analysis, no events above 3 keV are measured. This looks like a contradiction to the observation from the \(^{163}\)Ho-loaded pixels. However, the 95 % confidence intervals for the mean of the Poisson distribution are [0, 3.69) for no observations and [1.09, 10.24) for four counts. Accordingly, there is an overlap of the sets. \(^{166m}\)Ho can be excluded as background source, since a fraction of \(^{166m}\)Ho/\(^{163}\)Ho \( > 10^{-5}\) would be needed to explain these events [8] and is more than four orders of magnitudes higher than achieved. A fraction of \(10^{-4}\) can be achieved due to chemical purification [15] and a further reduction of five orders of magnitude by mass separation [16], resulting in a fraction of \(^{166m}\)Ho/\(^{163}\)Ho \( < 10^{-9}\). Measurements over a larger energy range are planned within the coming ECHo runs in order to be sensitive to structures at higher energies, which could be used to improve the understanding of the background sources. A \(^{163}\)Ho-like background can be observed in the spectrum recorded by the background pixels. This spectrum can be observed for each pixel and can neither be described by any simulations of natural radionuclides described in Sect. 6 so far or by muon caused events [12]. The measured spectrum could correspond to an activity of about \(30\,\upmu \)Bq of \(^{163}\)Ho per pixel, which corresponds to about \(6 \cdot 10^{6}\) atoms per pixel. The observed lines, which could represent the M lines around 2 keV and N lines round 400 eV of the \(^{163}\)Ho EC, are slightly shifted to lower energies compared to the \(^{163}\)Ho EC spectrum. Also, the fraction of number of events of the N line to the number of events of the M line of \(5 \pm 1\) is larger than expected from theory with 2.3. The energy shift of the lines and the higher N/M-ratio could be explained by \(^{163}\)Ho located at the surface of the background pixels, because multiple particles could be emitted by the decay. Further, if this is the case, a surface contamination of about 93 mBq cm\(^{-2}\) can be assumed for the whole detector chip. The endpoint region should not be affected by surface-distributed \(^{163}\)Ho, because the \(^{163}\)Ho activity in the pixels is five orders of magnitude higher than the potential surface contamination. If the source of this spectrum has different origins, a background level of about \(8 \cdot 10^{-5}\) pixel\(^{-1}\) day\(^{-1}\) can be assumed, since one event was measured between 2.5 keV and 3 keV in 241 pixel-days. In addition, the 1.49 keV line of aluminum X-rays could be observable.

Fig. 14
figure 14

Energy distribution of non-coincidental events measured by the background pixels. The blue spectrum shows all measured events. The orange spectrum shows the actual background spectrum

8 Summary

Different natural radionuclides were simulated in different parts of the ECHo set-up. The background in the ROI of the ECHo experiment is aimed to be dominated the unresolved pile-up of about \({10^{-6}}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI for the ECHo-1k phase with a \(^{163}\)Ho -activity per pixel of 1 Bq and a time resolution of 500 ns. The simulations show that concentrations of radionuclides of the order of 10 Bq kg\(^{-1}\) or a few hundreds of \(\upmu \)Bq cm\(^{-2}\) are needed to result in signal count rates as high as the signal due to the unresolved pile-up. Screening measurements were performed and concentration levels are given for connectors (which are not used in the simulations) and circuit boards. For copper, only upper limits are given, pointing out that the material is quite pure. The same can be expected for aluminum. In total, a count rate of about \({\left( 6 \pm 1 \right) \cdot 10^{-6}}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI due to naturally occurring radionuclides in materials in the next surrounding of the detector arrays. This value is higher than the rate of unresolved pile-up, but low enough for the ECHo-1k phase with an exposure of about less than one year. For the future stage of the ECHo experiment, ECHo-100k, different materials (Kapton) are foreseen as material for circuit boards. This should reduce the background due to natural radionuclides of about 90 %. Further, a \(^{163}\)Ho activity of a few Bq per pixel is foreseen, which increases the signal count rate as well as the pile-up.

Background measurements including \(^{163}\)Ho-loaded and -unloaded pixels were analyzed using pulse shape discrimination methods. Only events above the Q-value of the \(^{163}\)Ho EC are considered for data of \(^{163}\)Ho-loaded pixels, which can either be caused by unresolved pile-up events or by other sources. We measured a background level of about \({8 \cdot 10^{-5}}\) day\(^{-1}\) pixel\(^{-1}\) in the ROI. This count rate is higher compared to the pile-up limit and the expected background due to the simulated radionuclides and muons. On the other hand, the background pixels did not measure any events in the same energy region of above 3 keV. The spectrum measured by these background pixels could be caused by surface-distributed \(^{163}\)Ho with about 30 \(\upmu \)Bq per pixel, from which a count rate of less than \(10^{-8}\) day\(^{-1}\) pixel\(^{-1}\) is expected in the ROI.