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arxiv: 2605.04248 · v1 · submitted 2026-05-05 · ⚛️ physics.plasm-ph

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Synthetic model of gamma-ray emission during DT experiments on the SPARC tokamak

E.Panontin , R.A. Tinguely , J.L. Ball , A. Grieve , S. Mackie , L. Nichols , P. Raj , A.A. Saltos
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L. Singh D. Vezinet X. Wang J.C. Wright J. Rice
Authors on Pith no claims yet

Pith reviewed 2026-05-08 17:33 UTC · model grok-4.3

classification ⚛️ physics.plasm-ph
keywords gamma-ray spectroscopySPARC tokamakDT fusionneutron attenuatorLaBr3 detectorsfusion power reconstructionradiation transportfast ions
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The pith

LaBr3 detectors with a polyethylene attenuator can reconstruct DT fusion power in SPARC despite intense neutron flux.

A machine-rendered reading of the paper's core claim, the machinery that carries it, and where it could break.

The paper builds a synthetic model of gamma-ray production from DT and related reactions in SPARC's primary reference discharge, where fusion power reaches 140 MW. It uses TRANSP plasma profiles together with CQL3D and TORIC heating simulations to predict emission rates, then applies ray-tracing and Monte Carlo transport codes to test detector locations and background rejection. The model shows that a dedicated high-density polyethylene neutron attenuator raises the gamma-to-neutron ratio enough for lanthanum bromide scintillators to extract useful spectra. This enables direct inference of fusion power, fast-ion distributions, and heating performance from the observed gamma lines.

Core claim

Using TRANSP profiles and CQL3D/TORIC heating calculations, the model predicts gamma emission from the T(D, γ)He-5, B-10(He-4, p γ)C-13, and D(He-3, γ)Li-5 reactions. Radiation transport solved with ToFu, MCNP, and OpenMC identifies viable LaBr3 detector positions and demonstrates that a high-density polyethylene attenuator sufficiently suppresses the neutron background for the detectors to reconstruct the generated fusion power.

What carries the argument

Synthetic gamma emission model that couples TRANSP plasma profiles and CQL3D/TORIC heating with ToFu/MCNP/OpenMC radiation transport to evaluate LaBr3 detector performance and polyethylene attenuator design.

Load-bearing premise

The plasma profiles and fast-ion distributions calculated by TRANSP, CQL3D, and TORIC accurately represent the actual conditions that will occur in SPARC.

What would settle it

A side-by-side comparison of gamma spectra recorded by LaBr3 detectors during an actual SPARC DT discharge against the synthetic predictions, with independent fusion-power values from neutron diagnostics, would confirm or refute the model's signal-to-noise and reconstruction accuracy.

Figures

Figures reproduced from arXiv: 2605.04248 by A.A. Saltos, A. Grieve, D. Vezinet, E.Panontin, J.C. Wright, J.L. Ball, J. Rice, L. Nichols, L. Singh, P. Raj, R.A. Tinguely, S. Mackie, X. Wang.

Figure 1
Figure 1. Figure 1: Geometry of SPARC and NCAM LOS as imple￾mented in the OpenMC model (not to scale). More informa￾tion about the full model can be found in refs. [25, 26]. Starting from its first campaign, SPARC will be equipped with a hard X-ray (HXR) monitor [27, 28], which will use a LaBr3 crystal to measure photons in the MeV energy range. This diagnostic will pri￾marily be responsible to measure γ-rays emitted by brems… view at source ↗
Figure 2
Figure 2. Figure 2: Plasma profiles from ref. [35] for a SPARC plasma generating 110 MW of fusion power. (a) electron (ne), de￾terium (nD) and tritium (nT) densities. (b) electron (Te) and ion (Ti) temperatures. tercept the entire solid angle defined by the collima￾tors and the flux over the wetted area can be consid￾ered uniform. Since the wetted area is proportional to the square of the collimator diameter, then ToFu re￾sul… view at source ↗
Figure 3
Figure 3. Figure 3: (a) Poloidal profile of plasma yield for the D+T fusion reaction (both n and γ-ray branches included). First wall (solid line), LCFS (dashed line) and NCAM LOS (dashed lines) are shown with light-blue with top and bottom LOS labeled. (b) Expected rate of DT born, 16.7 MeV and 13.5 MeV γ-rays at the end of the NCAM collimators as calculated with ToFu. Three collimator diameters are considered: 1 cm (green),… view at source ↗
Figure 4
Figure 4. Figure 4: (a) From the TRANSP simulations in ref. [35]: density profiles of α-particles and 10B impurity (assuming B is present in the plasma at 1% of the electron density ne). (b) energy distribution of α-particles according to eq. (112) of ref. [41]. (c) interpolation of the 10B(α, p γ) 13C cross￾sections from refs. [23, 24]. Since fusion born α-particles are emitted with an en￾ergy of 3.5 MeV, we can approximate … view at source ↗
Figure 5
Figure 5. Figure 5: Left column: poloidal profile of plasma yield for the: (a) 3.09 MeV, (c) 3.68 MeV, and (e) 3.85 MeV γ-ray emissions of the α + 10B nuclear reaction. First wall, LCFS and NCAM LOS are shown with light-blue with top and bottom LOS labeled. Right column: expected rate of α 10B born, (b) 3.09 MeV, (d) 3.68 MeV, and (f) 3.85 MeV γ-rays at the end of the NCAM collimators as calculated with ToFu. Three collimator… view at source ↗
Figure 6
Figure 6. Figure 6: CQL3D+TORIC simulations from ref. [39]. (a) ICRH power density deposited in the plasma (PICRH), γ-ray yield for the D3He reaction (YD3He), density of the fast population of 3He (n fast 3He), and average energy of the fast population of 3He (E avg 3He). The maximum of all profiles is normalize to 1.(a) Energy distribution of the high energy tail of 3He at different radial locations view at source ↗
Figure 7
Figure 7. Figure 7: (a) Poloidal profile of plasma yield for the D+3He fusion reaction. First wall, LCFS and NCAM LOS are shown with light-blue with top and bottom LOS labeled. (b) Expected rate of DT born, 16.4 MeV γ-rays at the end of the NCAM collimators as calculated with ToFu. Three collimator diameters are considered: 1 cm (green), 2 cm (orange), 3 cm (blue). 8 view at source ↗
Figure 8
Figure 8. Figure 8: (a) Poloidal profile of plasma yield for the DD fusion reaction (all branches included). First wall, LCFS and NCAM LOS are shown with light-blue with top and bottom LOS labeled. (b) Expected rate of DT born, 23.8 MeV γ-rays at the end of the NCAM collimators as calculated with ToFu. Three collimator diameters are considered: 1 cm (green), 2 cm (orange), 3 cm (blue). 9 view at source ↗
Figure 9
Figure 9. Figure 9: shows the rates of 14.1 MeV reaching the end of the NCAM collimators during a PRD as calculated by ToFu. The profile is peaked at the central LOS of the NCAM, which has a collimator diameter of 3 cm and is expected to receive 3.3 × 1010 n/s. The work￾flow used to perform these calculations is the same used in section 2.1. The neutron rates reaching the end of the central NCAM collimator for two different p… view at source ↗
Figure 10
Figure 10. Figure 10: OpenMC simulations of the energy spectrum of prompt γ-rays generated in the torus hall that reaches the end of the NCAM collimators during a PRD. Shaded region shows interval of confidence. Due to the high neutron emissivity in the compact SPARC volume, the prompt-gamma background from the torus would be in excess of 5 × 105 γ/s even during a Q>1 discharge with a D = 1 cm collima￾tor. To reduce the expect… view at source ↗
Figure 11
Figure 11. Figure 11 view at source ↗
Figure 12
Figure 12. Figure 12: (a) LaBr3 detector response function to γ0 and γ1 emitted in DT fusion reactions. Both spectra are normalized per source photon emitted by the plasma. The spectrum of the DT emission in the plasma (source γ0 and source γ1) is the one measured in Ref. [33] and is normalized to unity. (b) Total spectrum measured by a LaBr3 detector during a PRD scenario. angle defined by the collimators and to stop the fast… view at source ↗
Figure 13
Figure 13. Figure 13: Total DT γ-rays that a LaBr3 detector is expected to measure above 10 MeV in a time interval ∆t. (a) considers 124 cm of HDPE neutron attenuator for PRD scenarios. (b) considers 38 cm of HDPE neutron attenuator for Q>1 scenarios. Contour lines for total DT γ-ray counts over the neutron background (N) and the Poisson statistics uncertainty related to the measurement (δP ) are also shown. the statistical un… view at source ↗
Figure 14
Figure 14. Figure 14: Expected spectrum integrated for 10 s of the α 10B γ-ray as measured by a LaBr3 detector behind 124 cm of HDPE attenuator (γ(α 10B)). Magnitude of the noise ex￾pected for the neutron-induced background in that energy range (noise). 5 Conclusions This paper studies the γ-ray emission during DT oper￾ations on SPARC and scopes the opportunity of mea￾suring it with traditional LaBr3 detectors. We present a wo… view at source ↗
read the original abstract

In thermonuclear plasmas, plasma ions undergoing nuclear reactions emit gamma-rays with energies in the MeV range. Their spectroscopy can convey much plasma information, such as the DT fusion power, the spatial and velocity distributions of the fast ions, and the plasma heating performance. In the present work, we simulate the gamma-ray emission expected in the SPARC tokamak during a primary reference discharge, when the tokamak is expected to generate $140$ MW of fusion power and reach an energy gain factor of $Q\approx11$. We focus particularly T(D, $\gamma$)He-5, B-10(He-4, p $\gamma$)C-13 and D(He-3, $\gamma$)Li-5 reactions. We use realistic plasma profiles calculated with the TRANSP code and simulate radiofrequency heating of the plasma with CQL3D and TORIC. Possible locations for gamma spectrometers based on lanthanum bromide inorganic scintillators are suggested. For each, the signal-to-noise ratio of gamma-rays over neutrons is evaluated using the ray-tracing code ToFu and high fidelity Monte Carlo models (MCNP and OpenMC) to solve radiation transport in SPARC. A dedicated neutron attenuator made of high density polyethylene is scoped to allow gamma-spectroscopy during high neutron yield experiments. And finally, the performance of LaBr$_3$ detectors in reconstructing the fusion power generated by SPARC is discussed.

Editorial analysis

A structured set of objections, weighed in public.

Desk editor's note, referee report, simulated authors' rebuttal, and a circularity audit. Tearing a paper down is the easy half of reading it; the pith above is the substance, this is the friction.

Referee Report

1 major / 3 minor

Summary. The manuscript presents a synthetic modeling workflow for gamma-ray emission in the SPARC tokamak during a high-power DT reference discharge (140 MW fusion power, Q≈11). It combines TRANSP-derived plasma profiles with CQL3D and TORIC simulations of RF heating to predict gamma yields from T(D,γ)⁵He, ¹⁰B(α,pγ)¹³C, and D(³He,γ)⁵Li reactions; uses ToFu, MCNP, and OpenMC to compute signal-to-noise ratios at candidate LaBr₃ detector locations; scopes a high-density polyethylene neutron attenuator; and evaluates the detectors' ability to reconstruct fusion power.

Significance. If the underlying profiles prove representative, the work supplies a practical framework for gamma-ray diagnostic design in high-neutron-yield tokamaks, demonstrating how a dedicated attenuator can enable spectroscopy and power reconstruction where direct measurements would otherwise be overwhelmed by neutron background. The multi-code integration and explicit focus on detector performance constitute a useful contribution to SPARC diagnostic planning.

major comments (1)
  1. [Plasma profile and heating modeling sections] The quantitative results on gamma-ray yields, SNR values, attenuator thickness, and fusion-power reconstruction accuracy all rest on the ion density, temperature, and fast-ion distributions supplied by TRANSP (reference discharge), CQL3D, and TORIC. No sensitivity studies or alternative profile sets are reported to quantify how deviations in anomalous transport, wave damping, or fast-ion tail shape would propagate into the reported gamma rates or required attenuator design. This assumption is load-bearing for the central claims about detector performance and attenuator scoping.
minor comments (3)
  1. [Abstract] Abstract: reaction notation is inconsistent and poorly formatted (e.g., “T(D, γ)He-5”, “B-10(He-4, p γ)C-13”). Standard LaTeX notation such as T(D,γ)⁵He and ¹⁰B(α,pγ)¹³C should be used throughout.
  2. [Abstract] The final sentence of the abstract begins with “And finally,” which is stylistically awkward; rephrase for conciseness.
  3. [Detector performance discussion] Figure captions and text should explicitly state the assumed detector energy resolution and efficiency curves used in the SNR and power-reconstruction calculations, as these parameters directly affect the claimed performance.

Simulated Author's Rebuttal

1 responses · 0 unresolved

We thank the referee for their constructive review and for recognizing the practical value of the multi-code workflow for gamma-ray diagnostic scoping in SPARC. We address the single major comment below.

read point-by-point responses

  1. Referee: The quantitative results on gamma-ray yields, SNR values, attenuator thickness, and fusion-power reconstruction accuracy all rest on the ion density, temperature, and fast-ion distributions supplied by TRANSP (reference discharge), CQL3D, and TORIC. No sensitivity studies or alternative profile sets are reported to quantify how deviations in anomalous transport, wave damping, or fast-ion tail shape would propagate into the reported gamma rates or required attenuator design. This assumption is load-bearing for the central claims about detector performance and attenuator scoping.

    Authors: We acknowledge that the reported gamma yields, SNR values, attenuator thickness, and power-reconstruction accuracy are derived from the specific TRANSP profiles of the SPARC primary reference discharge (140 MW fusion power, Q≈11), with fast-ion distributions obtained from CQL3D and TORIC. These profiles constitute the baseline scenario adopted by the SPARC team for high-performance DT planning. Comprehensive sensitivity scans over anomalous transport coefficients, wave-damping variations, or alternative fast-ion tail shapes were not performed, as they would require a separate, computationally intensive campaign of TRANSP/CQL3D/TORIC runs outside the scope of the present diagnostic-modeling paper. In the revised manuscript we will add a new subsection (likely in Section 2 or 4) that (i) explicitly states the reference-discharge assumption, (ii) cites the range of profile uncertainties documented in prior TRANSP studies of similar high-Q scenarios, and (iii) provides a qualitative estimate of how ±20 % variations in central ion temperature or fast-ion density would affect the T(D,γ)⁵He and ¹⁰B(α,pγ)¹³C yields and the resulting SNR at the candidate detector locations. This addition will allow readers to assess the robustness of the detector and attenuator conclusions without changing the quantitative results for the reference case. revision: partial

Circularity Check

0 steps flagged

No circularity: forward simulations driven by external profiles and codes

full rationale

The derivation begins with plasma profiles and fast-ion distributions supplied by TRANSP for the reference discharge, RF heating modeled independently by CQL3D and TORIC, and standard nuclear reaction cross-sections. These feed forward into gamma emission rates for the listed reactions, then into radiation transport via ToFu, MCNP, and OpenMC to compute signals, SNR, and attenuator performance. No equation or step defines the reported gamma yields, SNR values, or fusion-power reconstruction accuracy in terms of quantities that are themselves outputs of the same model; the chain remains a one-way synthetic prediction from independent inputs.

Axiom & Free-Parameter Ledger

0 free parameters · 2 axioms · 0 invented entities

The central claim rests on the fidelity of the input plasma profiles and the accuracy of the nuclear reaction rates and radiation transport physics already implemented in the cited codes. No new particles or forces are postulated.

axioms (2)
  • domain assumption TRANSP, CQL3D, and TORIC produce sufficiently accurate ion density, temperature, and fast-ion distributions for the SPARC primary reference discharge.
    These profiles are used as direct input to the gamma-emission calculation.
  • standard math The nuclear reaction rates and gamma branching ratios for T(D,γ)He-5, B-10(He-4,pγ)C-13, and D(He-3,γ)Li-5 are known to sufficient precision.
    The model relies on tabulated cross-sections without re-deriving them.

pith-pipeline@v0.9.0 · 5613 in / 1611 out tokens · 40797 ms · 2026-05-08T17:33:05.347823+00:00 · methodology

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