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The effects of a revised operational dose quantity on the response characteristics of neutron survey instruments

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Published 24 April 2018 © 2018 IOP Publishing Ltd
, , Citation J S Eakins et al 2018 J. Radiol. Prot. 38 688 DOI 10.1088/1361-6498/aaae1c

0952-4746/38/2/688

Abstract

The ICRU is considering revising the definition of ambient dose equivalent. This paper investigates the impacts of the proposed change on four designs of neutron survey instrument, the GNU, HSREM, LB6411 and Studsvik 2202D, in terms of their respective energy dependences of response and their performances in realistic workplace fields. In some circumstances the current designs of instrument still produce acceptable characteristics, but in general they may need to be re-optimized to better match the requirements of the new operational quantity; to that end, a simple retrofit solution for the GNU is demonstrated. The performance criteria against which instruments are judged may also need to be revised to reflect the proposed change.

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Introduction

At sites where neutron fields may be present, such as nuclear facilities or accelerator halls, it is essential to monitor dose rates to ensure that the risk to personnel is kept minimal. Typically, dose rate mapping in these fields is achieved through the use of neutron survey instruments, i.e. portable neutron monitors. At present, neutron survey instruments are calibrated in terms of ambient dose equivalent, H*(10), a quantity intended specifically for the monitoring of penetrating radiation doses in the workplace.

Ambient dose equivalent is defined by the International Commission on Radiation Units and Measurements (ICRU) in terms of the Q(L)-weighted dose at a depth of 10 mm in the ICRU tissue-equivalent sphere from an expanded and aligned radiation field [1]. The ambient dose equivalent per fluence, H*(10)/Φ, conversion coefficients were calculated [2] by ICRU using the kerma approximation, which is incorrect from a technical perspective due to fundamental differences between kerma and absorbed dose. However, when the current conversion coefficients [2] were calculated, coupled neutron-proton transport was not well developed within Monte Carlo software, and in any case at a 10 mm tissue depth the kerma conditions do not breakdown for neutrons until over 30 MeV [3], so for most workplace fields the data were acceptable. Correct calculation of the quantity, using full secondary charged particle transport within Monte Carlo models in a vacuum, would prevent it from providing a properly conservative assessment of the protection quantity effective dose, E, at higher energies because the ranges of the secondary charged particles, and in particular the secondary protons, would cause the maximum dose equivalent in tissue to be deposited at a depth significantly greater than 10 mm. Despite this, for some radiation fields H*(10)/Φ is still less than E/Φ, and hence does not adequately quantify the risk to individuals; geometric differences between the 30 cm diameter ICRU sphere and an anthropomorphic phantom are obvious causes of the discrepancies, but other factors are also relevant, in particular the excessive radiation weighting (wR) applied to lower-energy neutrons in the ICRP Publication 60 formulation of effective dose [4]. This latter problem will be reduced when the new wR relationship from ICRP Publication 103 [5] is incorporated into national legislations.

For some exposures H*(10)/Φ is several times larger than E/Φ leading, potentially, to the implementation of unnecessary safety measures and controls. This is true of thermal neutrons, for example, which penetrate quite effectively to 10 mm in tissue, but which are strongly attenuated before they reach most of the radiosensitive organs, so do not contribute strongly to effective dose. The magnitudes of these under- or over-estimates depend on both the energy and orientation of the exposure, because of the energy dependence of the effects described above and the direction dependence of effective dose.

In response to these limitations in the current definition of the operational quantity, ICRU has recently considered its revision [6, 7]. The proposed revision replaces H*(10) with a new quantity defined using an 'envelope function' over effective dose. The symbol for this new definition is H*, or equivalently Emax (used interchangeably in the current paper). The motivation for these changes is to make the dose quantities better reflect the risk associated with an exposure.

The suggested change to the operational dose quantity is just a proposal at this stage, and ICRU has not yet issued its final report on the definition. Nevertheless, it is inevitable that changing or abandoning H*(10) could impact upon many systems of dosimetry, including neutron survey instruments that are designed to respond in terms of it. The present paper investigates how the proposed change would affect a number of designs of instrument that are currently available commercially, and for one of them (the 'GNU'), discusses how its Emax response might be improved.

Data and method

Conversion coefficients

According to the proposed definition [6, 7], the fluence to dose conversion coefficient at a given energy, Emax/Φ (or equivalently H*/Φ), will be set equal to the maximum of the corresponding fluence to effective dose (EG/Φ) conversion coefficients at that energy taken over all geometries, G, considered by the International Commission on Radiological Protection (ICRP) [8], i.e. G denotes anterior-posterior (AP), posterior-anterior (PA), left-lateral (LLAT), right-lateral (RLAT), isotropic (ISO), semi-isotropic superior (SS-ISO), semi-isotropic inferior (SI-ISO), and rotational (ROT). A comparison of Emax/Φ and H*(10)/Φ as a function of neutron energy is shown in figure 1. Also shown in figure 1 is the quantity EAP/Φ, which in comparison to H*(10)/Φ demonstrates the motivation for the proposed new quantity.

Figure 1.

Figure 1. Comparison of the current quantities EAP/Φ and H*(10)/Φ, and the proposed new quantity Emax/Φ (or equivalently H*/Φ).

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For most of the energy range over which neutron survey instruments are often employed, i.e. from thermal to ∼20 MeV, H*(10) over-estimates the protection quantity; the magnitude of this discrepancy can vary from a ∼few percent between 1 and 10 keV, to a factor of ∼few at thermal energies. Although designing neutron survey instruments to respond in terms of H*(10) therefore provides an inherent degree of general conservatism in their routine use, in some workplace fields it can prove over-cautious. Moreover, for the energy range from ∼2 to ∼10 MeV, which is also close to the mean energies of the 241Am-Be or 252Cf sources typically used to calibrate them, and above ∼40 MeV, assessment of H*(10) significantly under-estimates the protection quantity, and hence the potential risk to the individual. Conversely, Emax/Φ is always conservative relative to EG/Φ, by definition, for all G. Further, unlike H*(10) for which the conservatism is somewhat 'artificial', the conservatism in Emax is arguably more grounded: Emax faithfully represents the largest possible value of effective dose in a given field for an individual orientated within it. On balance, therefore, for the overall meV to GeV energy range the proposed quantity Emax represents a more reliable assessment of potential risk to individuals than H*(10), with the advantages particularly significant in workplace fields featuring high energy neutrons.

Neutron survey instruments

For the purposes of the present exercise, four contemporary neutron survey instruments have been considered: the Berthold LB6411 [9], Studsvik 2202D [10], HSREM [11] and GNU [12]. There are many neutron survey instruments that could have been selected, but these were favoured because the GNU was recently designed at Public Health England (PHE), the LB6411 is widely used throughout Europe and is of relatively recent design, the Studsvik 2202D is representative of the Andersson-Braun family of instruments [13], and the HSREM is the newest variation of the Leake family of instruments [14, 15] based on relatively light spheres. The current manifestation of the Studsvik 2202D is the KWD Nuclear Instruments AB 2222A. The GNU, or 'Guided Neutron Unit', has recently been developed and is now commercially available: it has a flatter energy-dependence of H*(10) response than the other devices, is highly sensitive, and has a considerably better response to high-energy neutrons than instruments of comparable mass (∼8 kg, excluding electronics).

The dose response characteristics of these four devices have been calculated previously at selected neutron energies across a range spanning from meV to MeV, using H*(10)-per-fluence data applied to counts-per-fluence results obtained from Monte Carlo modelling; for the GNU, this energy range has been extended up to 1 TeV. The response characteristics of the instruments at those energies are now recalculated using Emax/Φ data in place of H*(10)/Φ.

In addition to their energy-dependent responses to monoenergetic sources, the performances of the four instruments in workplace fields have also been calculated and contrasted under the assumptions of the proposed change. This was achieved by convolving the respective fluence response characteristics of the devices with the 19 realistic workplace neutron fluence-energy distributions that were determined during the EVIDOS project [16], using a specially designed algorithm that 'folded' the relevant data pointwise across a suitably fine energy grid. Each result was then divided by the mean H*(10)/Φ or Emax/Φ (as appropriate) for that field, similarly derived by folding the distribution with the monoenergetic conversion coefficient data.

The H*(10) or Emax response of each instrument to241Am-Be and 252Cf calibration sources were also calculated by means of the same folding method, using reference fluence-energy distribution data [17].

Results

Calibration fields

The absolute H*(10) and Emax responses of the LB6411, Studsvik 2202D, HSREM and GNU are shown in figures 2(a) and (b) respectively, with data for the GNU presented both for isotropic exposures and for a plane-parallel exposure orientated opposite to the stem of its central, 3He-filled, LND detector [12]. The same data are presented in figures 3(a) and (b), but shown relative to each instrument's calculated H*(10) or Emax response, as appropriate, to 241Am-Be. The absolute H*(10) and Emax responses of the four devices to 241Am-Be and 252Cf sources are given in table 1.

Figure 2.

Figure 2. (a) H*(10) and (b) Emax responses of the LB6411, Studsvik 2202D, HSREM and GNU.

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Figure 3.

Figure 3. Relative (a) H*(10) and (b) Emax responses of the LB6411, Studsvik 2202D, HSREM and GNU, normalized to their respective responses to 241Am-Be. Recommended limits (solid lines), and the effects of recalibrations to the responses at 144 keV (dotted line) and 565 keV (dashed line), are also indicated.

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Table 1.  Conversion coefficient data and the H*(10) and Emax responses of the instruments to 241Am-Be and 252Cf.

  Conversion Coefficient (pSv cm2) GNU LB6411 Studsvik HSREM
SOURCE H*(10)/Φ Emax Ratio (H/E) Ha Eb Ha Eb Ha Eb Ha Eb
241Am-Be 391 427 0.92 5.92 5.43 2.94 2.69 0.97 0.88 7.05 6.47
252Cf 385 352 1.09 6.20 6.78 2.83 3.09 1.00 1.09 7.92 8.66

aH*(10) response (counts nSv−1). bEmax response (counts nSv−1).

It is seen in figures 2(a) and 3(a) that the GNU has the best H*(10) response for thermal neutrons and a relatively small over-response around 10 keV. However, this advantage would be reduced by a change to Emax: the responses of all of the instruments are flatter below ∼10 keV (figures 2(b) and 3(b)), but the change in the conversion coefficients for thermal neutrons gives the GNU a poorer response at that energy (figure 3(b)).

For the LB6411 and Studsvik 2202D, amending the dose quantity would lead to a slightly flatter energy-dependence of response, although the Studsvik is still less sensitive than the LB6411, which is in turn considerably less sensitive than the GNU. The response of the highly sensitive HSREM is also arguably improved by a change from H*(10) to Emax, though it is still more energy-dependent than the other designs, which is the penalty of being the lightest detector. For all four instruments, the differences are most manifest at low energies, though the 'dip' in H*(10) response at around 100 keV is also flattened by the change to Emax; the change neither improves nor exacerbates the significant over-response peaked at ∼5 keV that is typical in many designs of neutron survey instrument. Of course, these energy-dependent trends are as anticipated from figure 1, and result in part from the limitations in the use of H*(10) as a surrogate for the protection quantity, rather than from deficiencies in the designs of the instruments themselves.

In all cases, the relative responses of the instruments could potentially be improved by adopting a different calibration. This might be achieved by scaling the 241Am-Be response by a constant factor, chosen so that it provides a more optimal response characteristic across the energy range. An alternative approach might be to recalibrate to a different energy or source, though routine checking of the instrument would likely still need to use a readily available radionuclide such as 241Am-Be or 252Cf. Examples of this possibility are shown in figure 3(b), where the relative performance of the GNU is seen to be improved by renormalizing to its responses at either 144 or 565 keV, which were determined by interpolating the monoenergetic data (figure 2(b)). These calibration energies can readily be provided by most Primary Standards Laboratories for neutron exposures, for instance the UK's National Physical Laboratory (NPL) [18]. Indeed, a 'hybrid' approach might also be possible, such as routinely calibrating to 241Am-Be, say, but using its ratio with the 565 keV response to inform the choice of optimum scaling factor. Ultimately, however, these options are just compromises: in the current context, figure 3(b) illustrates that although recalibration may improve relative responses overall, it could not improve the energy dependence of an instrument's response and so cannot alone solve all of the limitations that would be introduced for the current designs of instruments upon adopting the new dose quantity.

The performances of neutron survey instruments are typically judged against criteria stipulated in international standards [19, 20]. The IEC standard recommends that the relative responses of instruments should lie between 0.2 and 8.0 in the energy range from thermal to 50 keV, between 0.5 and 2.0 from 50 keV to 10 MeV, and between 0.2 and 2.0 from 10 MeV to 20 MeV. These limits are shown on figure 3(a), where it is apparent that the instruments had acceptable response in terms of these criteria (though the HSREM does exceed them slightly at the keV scale), but that they no longer always satisfy the requirements when responding in terms of Emax (figure 3(b)); of course, these limits would need to be shifted proportionally if the alternative calibrations to 144 or 565 keV shown in figure 3(b) were adopted. However, the IEC criteria are given in terms of the H*(10) response, so it may be argued that they would not be an appropriate test for instruments calibrated to Emax. This leads naturally to the suggestion that changing the dose quantity from H*(10) to Emax would require corresponding amendments to the standards. For example, it may no longer be appropriate to permit a factor of 5 under-response for thermal neutrons, an important energy in many workplaces. This was allowed previously because, in terms of H*(10), there needed to be a balance between the under-response for thermals and the over-response around 10 keV. At the other extreme of the energy range, the high energy response of the GNU is seen to be significantly poorer for Emax than for H*(10), which will be hard to remedy without the addition of considerably more lead and hence more mass. The other instruments, which do not have response data available for high energies, would have poorer responses than the GNU, so they are unlikely to have acceptable performances above 20 MeV. This could cause problems for monitoring in workplace fields with high energy components, such as around accelerator or fusion facilities.

When deciding upon the optimum calibration for each instrument, if they are to be judged against the same IEC 61005:2014 [19] criteria, there are clearly a number of problematic energy ranges. Thermal neutrons will not present the difficulty that they did previously, but there will still be a potential for exceeding the IEC criteria at around 10 keV. Moreover, excessive response around 10 keV will make it hard for the design to meet the criteria at 50 keV. It is already hard for instruments to achieve a response >0.5 at 10 MeV, but this will be more difficult with Emax if they have no high-Z layer. Adoption of a different calibration to solve the response issue around 50 keV will make the 10 MeV issue more severe. Ultimately, it will be for the manufacturers of the instruments to consider carefully the calibration implications for their devices, with some compromise inevitably required. The examples given in this section are provided just for the purposes of discussion, and should not be misinterpreted as how each instrument would have to be calibrated if the new operational quantities were adopted.

Workplace fields

The H*(10)/Φ conversion coefficients for the 19 EVIDOS fields [16] were all larger than their Emax/Φ counterparts: an average ratio of ∼1.6× was found, with the largest nearly a factor of 2 (table 2). This is because the workplace fields are dominated by components with energies less than a few MeV, for which H*(10) provides excessively conservative estimates of E (figure 1). Regardless, the observation demonstrates the point that changing the dose quantity will effectively change the perceived characteristics of radiation fields, and not just the responses of instruments used within them.

Table 2.  Conversion coefficient data and the H*(10) and Emax responses of the instruments in the 19 EVIDOS fields, given relative to their respective responses to 241Am-Be. The EVIDOS field identifiers are those given in [16].

  Conversion Coefficient (pSv cm2) GNU LB6411 Studsvik HSREM
EVIDOS FIELD H*(10)/Φ Emax Ratio (H/E) RHa REb RHa REb RHa REb RHa REb
CANEL 44.5 26.4 1.69 1.10 2.02 0.78 1.43 0.97 1.78 1.40 2.58
SIGMA 22.3 14.9 1.49 0.98 1.59 0.66 1.07 0.78 1.28 0.97 1.58
C. NTL M 185 105 1.76 0.96 1.84 0.75 1.44 0.89 1.70 1.25 2.40
C. NTL S 156 89.7 1.74 0.98 1.87 0.76 1.45 0.91 1.73 1.29 2.45
BWR T 40.7 21.0 1.94 1.25 2.64 0.80 1.69 1.08 2.28 1.81 3.82
BWR SAR 37.1 20.1 1.85 1.36 2.74 0.88 1.78 1.19 2.40 2.00 4.04
BN 1 253 217 1.16 1.05 1.34 0.94 1.19 1.03 1.31 1.16 1.48
BN 2A 260 212 1.23 1.04 1.39 0.91 1.22 1.01 1.35 1.17 1.57
BN 2B 142 103 1.39 1.04 1.57 0.86 1.30 0.99 1.49 1.24 1.87
BN 3 115 82.0 1.40 1.05 1.60 0.86 1.31 0.99 1.51 1.26 1.92
VENUS C 36.9 26.6 1.39 1.06 1.61 0.80 1.21 0.94 1.42 1.19 1.80
VENUS F 47.3 31.9 1.49 1.10 1.78 0.83 1.34 0.99 1.60 1.33 2.15
PWR A 29.7 15.5 1.92 1.30 2.71 0.81 1.69 1.10 2.30 1.84 3.85
PWR L 38.8 20.6 1.89 1.35 2.78 0.86 1.78 1.18 2.42 2.00 4.13
C. TN D 49.3 28.3 1.74 1.21 2.30 0.85 1.61 1.08 2.05 1.67 3.18
C. TN N 37.9 19.7 1.92 1.18 2.47 0.77 1.61 1.01 2.12 1.63 3.42
NF 1 116 81.9 1.41 1.07 1.64 0.86 1.33 1.00 1.55 1.30 2.00
NF 2 55.3 37.8 1.47 1.12 1.79 0.85 1.36 1.02 1.63 1.38 2.21
NF 3 194 147 1.32 1.04 1.50 0.89 1.27 1.00 1.44 1.22 1.76
Mean 97.9 68.4 1.59 1.12 1.96 0.83 1.43 1.01 1.76 1.43 2.54
Std. Deviation 76.4 62.6 0.25 0.12 0.48 0.06 0.21 0.09 0.38 0.30 0.89

aRelative H*(10) response. bRelative Emax response.

The H*(10) and Emax responses of the instruments to the 19 EVIDOS workplace fields are shown in table 2, given relative to their respective responses to 241Am-Be. The mean of each set of H*(10) or Emax responses for the fields is also given for each instrument, along with the standard deviations of those 19 results around their average. The performances of the instruments can be seen to differ to greater or lesser extents, depending on the energy characteristics of both the fields [16] and the instrument responses (figures 2 and 3). However, one obvious trend is that the relative Emax responses of the four instruments in the workplace fields are all greater than their relative H*(10) responses, which is expected from the comparison of the H*(10)/Φ and Emax/Φ conversion coefficients. A second obvious trend is that the 19 H*(10) response results for a given instrument are generally distributed closer to their mean than those for Emax, with wider dispersals typically evidenced in the latter datasets. This weaker consistency for Emax relative to H*(10) is caused not just by differing response characteristics for the instruments, but also by differing characterizations of the fields themselves due to the amended dose quantity.

For a given instrument, the mean response value (table 1) could be reinterpreted as the factor by which the response should be increased relative to that for 241Am-Be to achieve optimum performance in the workplace. However, the selection of EVIDOS fields used does not include any very hard distributions, so it does not seem appropriate to make assumptions about how the manufacturers might individually choose to deal with this issue.

The LB6411 over-responds the least to Emax, but always under-responds to H*(10) for this selection of fields, in part because of its low response to thermal neutrons. A second cause of the under-response is the choice of normalization: for the LB6411 it is typically preferable to calibrate to 252Cf rather than 241Am-Be. However, although it can be shown from the data in tables 1 and 2 that this would improve the under-response to H*(10), with the mean relative response increasing from 0.83 for 241Am-Be to 0.86 for 252Cf, for example, there is still a significant over-response to Emax, although the mean relative response would decrease from 1.43 for 241Am-Be to 1.24 for 252Cf.

The GNU and Studsvik are comparable in performance, over-responding to Emax by average factors of ∼2.0× and ∼1.8× respectively. The HSREM significantly over-responds to Emax, but it also over-responds to H*(10) in 12 out of the 13 fields.

In all cases, the over-responses shown in table 2 could potentially be reduced by routine recalibration to a source other than 241Am-Be, or by rescaling the 241Am-Be calibration by a constant factor. Similarly to before (figure 3(b)), examples of such alternative calibration sources might be 144 keV or 565 keV, both of which would roughly halve the results. To illustrate this possibility, the Emax responses of the GNU to workplace exposures have been renormalized to its responses at both 144 keV and 565 keV. The recalibrated responses are shown in figure 4, alongside the Emax and H*(10) results for the usual 241Am-Be normalization (table 2); each datapoint is plotted at the mean H*(10)/Φ or Emax/Φ (as appropriate) for that field. The figure indicates relative pros and cons between using either 144 keV or 565 keV calibrations for Emax, but both clearly produce datasets that are generally much closer to unity than that for 241Am-Be. Of course, as before (figure 3(b)), these recalibrations are chosen to demonstrate general trends and are not necessarily considered optimal.

Figure 4.

Figure 4. H*(10) and Emax relative responses of the GNU in the EVIDOS workplace fields.

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Potential improvements for the GNU

One major innovation of the GNU compared to other survey instruments is the inclusion of six internal air-filled guides (figure 5) that channel neutrons directly to the central detector, greatly increasing its sensitivity at low-energies; these guides are capped by hemi-spherical plugs that minimize differences between the instrument's responses in plane-parallel and isotropic fields [12, 21]. Reduction of the size of these guides, or enlargement of the plugs, are obvious suggestions to suppress the over-response to Emax observed at low energies (figures 23). Figure 6 shows the Emax response of a modified version of the GNU that features plugs that are roughly twice the thickness of those in the current design; the results for this trial design were determined using the Monte Carlo modelling code MCNP6 [22]. Such a modification of the plugs is seen to reduce the low-energy over-response without detriment to the performance at higher energies, and would be easy to retrofit to the present design of instrument.

Figure 5.

Figure 5. Cross-sectional schematic of the spherical GNU survey instrument, viewed in a plane through four of the six air-filled neutron guides [white]; the remaining two radiate perpendicularly in and out of the page. Lead [black], polyethylene [light grey] and Borotron® [dark grey] spherical shells surround the central 3He-filled LND detector, the stem of which passes through the guide on the right. The guides are capped by hemispherical plugs.

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Figure 6.

Figure 6. H*(10) and Emax relative responses of the current GNU design, and the Emax relative response for a trial featuring modified 'plugs'.

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The GNU also incorporates a thin layer of lead around its central detector that boosts the response to high energy neutrons. It is likely that increasing the thickness of this layer would improve the serious under-response to Emax exhibited at these energies. However, investigation of such a possibility would be part of a full re-optimization campaign for the GNU that would involve balancing this change against concurrent modifications to its moderator and attenuator layers [12, 21], as well as to the guides and plugs, to better match the demands of the new quantity. This work is beyond the scope of the current paper and, in any case, would be premature before publication of the final recommendations by ICRU. Presumably, the manufacturers of other instruments may likewise choose to remodel their designs at that stage.

Summary/conclusions

There are energies for which H*(10) would lead to a significant under-estimate of risk to individuals in neutron fields (figure 1), providing motivation for the change to the operational dose quantity being proposed by ICRU. It is, however, inevitable that calibrating neutron survey instruments in terms of Emax will lead to response characteristics that are significantly different from those obtained when calibrated in terms of H*(10). The impacts of this change for the GNU, HSREM, LB6411 and Studsvik 2202D are shown for monoenergetic exposures in figures 23 and for workplace fields in table 1. Clearly, the respective responses to Emax differ depending on the energy characteristics of both the fields and the device, and are anticipated from the observation that both under- and over-responses to H*(10) are exhibited by the instruments across their energy ranges of applicability.

For some instruments, their current design might still produce performances that could be considered acceptable, though choosing an alternative calibration source, or multiplying the response to 241Am-Be or 252Cf by an appropriate scaling factor, might be preferable (figures 34). But in general the shape, size and materials comprising an instrument may need to be re-optimized to better match the requirements of the new dose quantity. A simple such change for the GNU, namely an increase in the thickness of the plugs that cap its internal neutron guides, has been shown to greatly improve the Emax response at low energies (figure 6), and could readily be retrofitted to the current design.

Ultimately, the effectiveness of any re-optimization campaign for a given device would be judged against the performance criteria currently stipulated for neutron survey instruments [19, 20]. However it is remarked that those criteria would, in time, also preferably be updated to better reflect the requirements of the proposed dose quantity. In turn, the radiation licensees who utilize neutron survey instruments may likewise need to recalibrate or replace their existing equipment with the updated versions, in order to better assess the new dose quantity in their respective workplace fields and comply with new recommendations once accepted. The logistics, timescale and financial implications of such a renewal programme would likely vary on a case-by-case basis, but indicate that the potential benefits of moving from H*(10) to Emax in terms of more accurate risk assessments would inevitably be weighed against potential costs.

It may prove to be the case that the new operational quantity opens up better options for neutron survey instrument design, either by adjustments to the existing designs or by making more radical redesign feasible. The biggest challenge in designing moderator type instruments, with a single central detector, has been to balance thermal neutron under-response with over-response in the 5–10 keV energy range. This has required features such as perforated thermal neutron attenuators and neutron guides to get the thermal neutrons to the detector without allowing keV-scale neutrons to be detected too efficiently. In practice, this need was caused by the operational quantity overestimating the risk from thermal neutrons by an excessive amount. The proposed dose quantity will make this aspect of design less challenging.

Conversely, higher-energy performance requirements will be harder to satisfy if the new quantity is adopted. It may drive designs towards heavier instruments, because it will be easier to meet the requirements around 10 MeV by using larger diameter moderators, by introducing high-Z materials, or by increasing the mass of high-Z materials already used.

Acknowledgments

The authors thank John Leake and Bob Mason (Sherwood-Nutec Scientific Ltd) for collaborative work on the GNU.

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10.1088/1361-6498/aaae1c