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Neutron emission

Neutron emission is a type of radioactive decay in which an unstable atomic nucleus spontaneously ejects one or more neutrons to achieve a more stable configuration, resulting in a daughter nucleus that retains the same atomic number but has a mass number reduced by the number of neutrons emitted.^[1]^[2] This process does not change the element but produces a different isotope, and it is particularly characteristic of neutron-rich, proton-poor nuclei located beyond the neutron drip line.^[2]^[3] Neutron emission can occur through several mechanisms, including direct spontaneous emission from highly unstable isotopes, though this is rare and typically observed in exotic, neutron-excessive nuclides such as beryllium-13, which decays to beryllium-12 plus a neutron, or nitrogen-24 to nitrogen-23 plus a neutron.^[3]^[4] More commonly, it arises during nuclear reactions like fission, where prompt neutrons are released almost instantaneously (within about 10^{-14} seconds) from the fissioning nucleus, or as delayed neutrons emitted following the beta decay of fission fragments.^[1]^[5] In thermal-neutron-induced fission of uranium-235, for instance, an average of 2.42 neutrons are emitted per event, with approximately 0.65% being delayed neutrons from precursors like bromine-87.^[5] Other contexts include inelastic scattering reactions, such as (n, 2n) processes, where an incoming neutron excites the nucleus, leading to the emission of multiple neutrons.^[1] The phenomenon plays a pivotal role in nuclear physics and engineering, particularly in sustaining chain reactions within nuclear reactors, where prompt neutrons drive rapid energy release while delayed neutrons—originating from over 200 known beta-delayed neutron emitters—provide essential controllability to prevent supercriticality.^[1]^[5] Neutron emission is also harnessed in specialized sources, such as californium-252, which undergoes spontaneous fission to release an average of 3.8 neutrons per event, enabling applications in neutron radiography, activation analysis, and medical isotope production.^[6] Beyond energy production, it contributes to astrophysical processes like nucleosynthesis in neutron star mergers and informs studies of nuclear structure in far-from-stability isotopes.^[5]

General Principles

Definition and Characteristics

Neutron emission is a nuclear process in which an atomic nucleus ejects one or more neutrons, typically from an excited or unstable state, resulting in a daughter nucleus that retains the same atomic number Z but has its mass number A decreased by the number of neutrons emitted.^[1] This decay mode is characteristic of neutron-rich or highly excited nuclei seeking greater stability by shedding excess neutrons.^[2] Key characteristics of neutron emission include the neutral charge of the emitted particles, which allows them to penetrate deeply into materials without interacting via the electromagnetic force, unlike charged particles such as alpha or beta particles.^[7] The kinetic energies of these neutrons generally range from hundreds of keV to several MeV, influenced by the nuclear excitation energy and reaction dynamics.^[8] This process plays a role in nuclear reactions, radioactive decays, and fission, contributing to chain reactions in reactors and stellar nucleosynthesis.^[1] Historically, the neutron's existence was confirmed in 1932 by James Chadwick, who interpreted neutral radiation from alpha-beryllium interactions as arising from a massive, uncharged particle within the nucleus. In contrast to alpha emission, which ejects a helium nucleus and decreases both Z by 2 and A by 4, or beta emission, which transforms a neutron into a proton (or vice versa) and alters Z by 1 while preserving A, neutron emission uniquely maintains the atomic number while reducing the mass number.^[9] Basic examples include neutron ejection from excited states formed in radiative capture reactions like (n,γ), where the compound nucleus deexcites partly via neutron evaporation, or from unstable configurations such as excited states of isotopes like ^{17}O.^[10]

Energy Considerations and Kinematics

Neutron emission from a nucleus requires overcoming the neutron separation energy S_n, which is the minimum energy needed to detach a neutron, leaving the daughter nucleus in its ground state. This energy is given by the mass difference formula

S_n(^{A}_{Z}\text{X}) = \left[ M(^{A}_{Z}\text{X}) - M(^{A-1}_{Z}\text{X}) - m_n \right] c^2,

where M denotes atomic masses in energy units, m_n is the neutron mass, and c is the speed of light.^[11] For heavy nuclei, S_n typically ranges from 5 to 8 MeV, reflecting the balance between nuclear binding and the Coulomb barrier's negligible role for neutrons.^[12] Emission becomes possible when the parent nucleus is excited to an energy E^* \geq S_n, as occurs in reactions or decays. The Q-value for the neutron emission reaction ^{A}_{Z}\text{X} \to ^{A-1}_{Z}\text{X} + n is Q = -S_n, signifying an endothermic process from the ground state. From an excited state, the total available energy for the products' kinetics is E_{av} = E^* - S_n, assuming the daughter is left in its ground state; if populated in an excited state, E_{av} decreases accordingly.^[13] This Q-value framework determines whether emission competes with other de-excitation modes like gamma emission. In the rest frame of the parent nucleus, neutron emission approximates a two-body decay, governed by energy and momentum conservation. The neutron kinetic energy is

E_n = E_{av} \cdot \frac{M_d}{M_d + m_n},

and the daughter recoil energy is

E_r = E_{av} \cdot \frac{m_n}{M_d + m_n},

where M_d is the daughter mass; for heavy parents, E_n \approx E_{av} since M_d \gg m_n.^[13] Momentum conservation imposes \mathbf{p}_n = -\mathbf{p}_r, with magnitudes |\mathbf{p}_n| = |\mathbf{p}_r| = \sqrt{2 \mu E_{av}}, where \mu = m_n M_d / (M_d + m_n) is the reduced mass. Relativistic corrections apply for E_n > 10 MeV, adjusting energies via Lorentz factors, though non-relativistic kinematics suffice for most nuclear emission scenarios below 20 MeV.^[13] This results in discrete neutron energy spectra when transitions target specific daughter levels, broadened by the finite parent excitation width. The probability of neutron emission is modulated by the daughter nucleus's level density, which dictates the available final states and thus the phase space, and by angular momentum conservation, which favors low-\Delta l transitions to minimize centrifugal barriers. Higher level densities near the Fermi level enhance emission rates via increased statistical weight in Hauser-Feshbach formulations.

Spontaneous Neutron Emission

Single Neutron Emission

Single neutron emission refers to the spontaneous ejection of a single neutron from an unstable nucleus without external stimulation, a process observed primarily in neutron-rich isotopes beyond or near the neutron drip line. This decay mode becomes possible when the neutron separation energy S_n < 0, rendering the ground or low-lying excited state unbound to neutron decay, or when the nucleus is in a highly excited state above the drip line following production in reactions. Unlike charged particle emissions, neutrons face no Coulomb barrier, leading to rapid decay for s-wave (l=0) emissions with lifetimes typically on the order of $10^{-21} seconds or shorter; however, for higher angular momentum states (l > 0), a centrifugal barrier necessitates quantum tunneling, which can extend lifetimes to measurable scales in specialized experiments. The strong nuclear binding in stable isotopes suppresses this process, making it exceedingly rare outside extreme neutron excess conditions.^[2]^[14] Key examples include low-lying neutron-unbound states in light, neutron-rich nuclei such as ^{12}\mathrm{Be}, where a resonance at 1243 ± 21 keV excitation energy decays to ^{11}\mathrm{Be} + \mathrm{n} with a width of 634 ± 60 keV, indicating a short but observable lifetime. Similarly, in ^{31}\mathrm{[Ne](/page/Ne)}, excited states near the drip line emit single neutrons, with resonances identified at energies around 0.30 MeV and 1.50 MeV, produced via two-proton knockout reactions from ^{33}\mathrm{Mg}. In heavier systems, neutron-rich fragments from projectile fragmentation reactions often de-excite via single neutron emission as they cool, contributing to the population of unbound states in isotopes like ^{31}\mathrm{[Ne](/page/Ne)} or ^{17}\mathrm{C}. These cases highlight the process's relevance in exploring nuclear structure at the limits of stability.^[15]^[16]^[16] The probability and decay rates of single neutron emission are governed by the Gamow tunneling factor through the centrifugal barrier, yielding extremely low branching ratios, often below 0.1% when competing with beta decay or other modes in marginally unbound systems. Calculations incorporate the barrier penetrability P \approx \exp\left(-2 \int_{r_0}^{r_t} \sqrt{\frac{2\mu}{\hbar^2} (V(r) - E)} \, dr \right), where V(r) includes the nuclear potential and centrifugal term, resulting in partial half-lives ranging from femtoseconds to nanoseconds for observable resonances. Detection poses significant challenges due to low production yields and short lifetimes, requiring high-intensity radioactive ion beams and specialized neutron counters, such as time-of-flight spectrometers or position-sensitive scintillators, often in facilities like RIKEN or NSCL; underground laboratories with ultra-low background environments aid in isolating rare events from cosmic-ray-induced neutrons.^[14]^[17] Theoretical models, particularly the nuclear shell model, provide essential predictions for neutron-unbound states by computing single-particle orbitals and their widths beyond closed shells, such as the N=20 or N=28 gaps. For ^{31}\mathrm{Ne}, shell model calculations anticipate three low-lying states decaying via single neutron emission, with the $9/2^- state at 1.49 MeV showing the largest cross-section, aligning with experimental observations and aiding in mapping the island of inversion. These models emphasize the role of deformed configurations and continuum effects in enhancing emission probabilities near drip lines.^[16]^[18]

Double Neutron Emission

Double neutron emission, also known as two-neutron decay, is a rare spontaneous decay mode observed in neutron-rich nuclei beyond the neutron drip line, where two valence neutrons are emitted simultaneously in a direct three-body process. This mechanism arises primarily from strong pairing correlations between the neutrons, which promote their correlated ejection as a transient dineutron-like cluster rather than independent particles. The process is distinguished by the extremely short lifetime of any hypothetical intermediate state—less than $10^{-21} s—preventing sequential single-neutron emission and ensuring the decay proceeds as a genuine three-body breakup of the nucleus into a daughter core plus two neutrons.^[19]^[20] A prominent example is the ground-state decay of ^{16}Be to ^{14}Be + 2n, first experimentally confirmed in 2012 via single-proton knockout reactions from a ^{17}B beam at the National Superconducting Cyclotron Laboratory (NSCL). The two-neutron separation energy for this transition is measured at 1.35 ± 0.10 MeV, yielding a half-life on the order of $10^{-21} s, consistent with direct emission. Single-neutron emission to ^{15}Be is energetically forbidden, making double neutron emission the sole decay channel with a branching ratio of essentially 100%.^[21]^[22] In such decays, the two neutrons share the available energy, exhibiting relative kinetic energies up to several hundred keV and often emitted nearly back-to-back in the center-of-mass frame, a signature of their spatial correlation driven by pairing. Theoretical models, including three-body decay kinematics via hyperspherical harmonics expansions and dinuclear cluster approaches, successfully describe these features by incorporating neutron-neutron interactions and the core's structure. For other drip-line nuclei where competing channels exist, double neutron emission typically constitutes a branching ratio of 1–10%.^[19]^[20]^[23] Experimental evidence for the direct mechanism relies on high-resolution time-of-flight measurements with neutron detector arrays, such as the Modular Neutron Array (MoNA) coupled to a superconducting dipole, which detect the three-body final state without populating intermediate resonances in the ^{15}Be subsystem. These observations rule out sequential decay paths and highlight the role of pairing in stabilizing the dineutron configuration during emission.^[21]^[24]

Beta-Delayed Neutron Emission

Mechanisms

Beta-delayed neutron emission occurs when a neutron-rich precursor nucleus undergoes beta-minus decay, transforming a neutron into a proton, electron, and antineutrino (n → p + e⁻ + ν̄_e), which leaves the daughter nucleus in an excited state. If this excitation energy exceeds the neutron separation energy S_n of the daughter, the nucleus de-excites promptly by emitting one or more neutrons, typically within 10^{-12} to 10^{-9} seconds after the beta decay. The probability of neutron emission depends on the distribution of excitation energies populated during the beta decay, which is governed by the beta decay strength function and the available phase space above S_n.^[25] Key precursors are neutron-rich isotopes far from stability, such as ^{137}I, which undergoes beta decay to excited states in ^{137}Te, followed by neutron emission to form ^{136}Te with a probability P_n ≈ 7.1%. Approximately 250 such precursors have been identified, ranging from ^{8}He to ^{210}Tl, with the majority relevant to fission products in the mass range A ≈ 70–150. These precursors are classified into six groups based on their beta decay half-lives, as established by Keepin et al., with representative values of 0.20 s, 0.52 s, 1.50 s, 5.40 s, 16.0 s, and 55.6 s, allowing aggregation for reactor kinetics modeling.^[25]^[26] The neutron emission probability P_n for a given precursor is calculated using statistical models that integrate the nuclear level density ρ(E) with the neutron partial width Γ_n(E) over the accessible excitation energies, approximated as P_n = ∫ ρ(E) Γ_n(E) dE / ∫ ρ(E) Γ_tot(E) dE, where the integration is from S_n to the maximum beta decay energy Q_β, and Γ_tot includes competing decay channels like gamma emission. In fission contexts, individual P_n values for heavy precursors typically range from 0.1% to 5%, contributing to the overall delayed neutron yield of about 0.6–2% per fission event.^[27]^[25] The characteristic time delay for neutron emission arises from the precursor's beta decay half-life, spanning milliseconds to tens of seconds, which clearly separates these neutrons from prompt fission neutrons emitted on the timescale of 10^{-14} s. This delay is crucial for distinguishing the processes temporally. High-spin isomeric states in precursors, such as the (11/2)^- isomer in ^{137}I at 2.3 MeV, can further modify emission by altering beta decay branching ratios or populating different excitation cascades in the daughter, potentially suppressing or delaying neutron release due to angular momentum conservation.^[25]^[28]

Applications in Nuclear Reactors

In nuclear reactors, beta-delayed neutrons play a critical role in reactor kinetics by providing a small but essential fraction of the total neutrons produced during fission, typically around 0.65% for uranium-235 fueled systems.^[29] This minor contribution significantly extends the effective neutron lifetime from the prompt neutron generation time of approximately 0.001 seconds to about 0.1 seconds, allowing operators sufficient time to monitor and adjust reactor conditions through feedback control mechanisms. Without this delay, power excursions would occur too rapidly for effective intervention, rendering reactor operation unsafe. Beta-delayed neutrons originate from the decay of fission products, as briefly noted in the mechanisms of beta-delayed emission. The impact of beta-delayed neutrons is quantified through the effective delayed neutron fraction, β_eff, which is approximately 0.0065 for uranium-235. This parameter is incorporated into the point kinetics equations that model neutron population dynamics in reactors. The primary equation for neutron density n(t) is given by:

\frac{dn}{dt} = \frac{\rho - \beta}{\Lambda} n + \sum_{i=1}^{6} \lambda_i C_i

where ρ is the reactivity, β is the total delayed neutron fraction, Λ is the prompt neutron generation time, λ_i are the decay constants for the six precursor groups, and C_i are the precursor concentrations.^[30] These six groups account for the varying half-lives of precursors, from milliseconds to minutes, enabling accurate prediction of transient behaviors during reactivity insertions. Beta-delayed neutrons facilitate key control mechanisms in reactors, such as the insertion of control rods to absorb neutrons and achieve safe shutdown, often via a SCRAM procedure that rapidly reduces reactivity below the delayed neutron fraction threshold. This allows the reactor power to stabilize or decay over seconds rather than microseconds, critical for transient analysis and preventing uncontrolled excursions. In the 1986 Chernobyl incident, the reduced effective delayed neutron fraction due to fuel burnup and xenon poisoning contributed to an uncontrollable positive void coefficient, exacerbating the power excursion during the test.^[31] Modern reactor design relies on Monte Carlo simulations to model beta-delayed neutron effects, incorporating detailed precursor data to optimize core configurations and safety margins.^[32] Experimental validation often draws from facilities like the NRU reactor at Chalk River Laboratories, where delayed neutron measurements have informed kinetics parameters for advanced simulations.^[33] These approaches ensure precise evaluation of β_eff variations over the fuel cycle, enhancing overall reactor reliability.

Induced Fission

Induced fission occurs when a fissile nucleus, such as uranium-235, absorbs an incident neutron to form an excited compound nucleus, typically ^{236}U^*, which then undergoes fission. This process releases approximately 200 MeV of energy, with a portion partitioned into the kinetic energy of fission fragments and the excitation energy that leads to the prompt emission of 2-4 neutrons during or shortly after scission. The neutrons are emitted isotropically in the center-of-mass frame but appear anisotropic in the lab frame due to the motion of the fragments.^[34] The average number of prompt neutrons emitted per fission, denoted as \bar{\nu}, is approximately 2.4 for thermal neutron-induced fission of ^{235}U. This value accounts primarily for neutrons evaporated from the fully accelerated fragments post-scission, with contributions from pre-scission and scission neutrons being minor, typically less than 5% of the total. Including these minor components, the total neutron yield is around 2.5 neutrons per fission.^[35] The energy spectrum of these prompt fission neutrons is well-described by the Watt fission spectrum,

f(E) = C \exp\left(-\frac{E}{a}\right) \sinh\left(\sqrt{b E}\right),

where C is the normalization constant such that \int_0^\infty f(E) \, dE = 1, and for thermal fission of ^{235}U, the parameters are a = 0.988 MeV and b = 2.249 MeV^{-1}. This distribution yields an average neutron energy of about 2 MeV, with most neutrons having energies between 0.5 and 5 MeV.^[36] The neutron multiplicity \bar{\nu} increases with the energy of the incident neutron E_n, as higher excitation energy in the compound nucleus enhances neutron evaporation. For example, in fast neutron-induced fission of ^{238}U, which has a fission threshold around 1 MeV, \bar{\nu} rises from about 2.0 at threshold to over 4 at 200 MeV incident energy. This dependence is critical for fast reactor designs, where higher-energy neutrons can induce fission in otherwise non-fissile isotopes like ^{238}U.^[37]^[38] Experimental measurements of neutron multiplicity and spectra in induced fission are conducted using neutron beams from reactors and accelerators, such as the Los Alamos Neutron Science Center (LANSCE), where spallation neutrons induce fission in thin targets, allowing precise determination of energy-dependent yields via time-of-flight techniques. These data are essential for modeling chain reactions in nuclear reactors, where the prompt neutrons sustain criticality; for ^{235}U thermal fission, the effective multiplication factor k > 1 relies on \bar{\nu} exceeding the number of neutrons absorbed or lost per fission event.^[39]

Spontaneous Fission

Spontaneous fission occurs when a heavy atomic nucleus undergoes division into two or more lighter nuclei without external excitation energy, primarily driven by quantum mechanical tunneling through the nuclear fission barrier. This process is exceedingly rare for most actinides due to the high barrier height, resulting in extremely long half-lives. For example, in uranium-238 (^{238}\mathrm{U}), the branching ratio for spontaneous fission relative to alpha decay is approximately $5.45 \times 10^{-7}, corresponding to a spontaneous fission half-life of $8.2 \times 10^{15} years.^[40] The tunneling probability is highly sensitive to the barrier's shape and height, with the process originating from the ground state of the nucleus.^[41] Neutron emission accompanies spontaneous fission as the resulting fragments are typically neutron-rich and de-excite through prompt neutron evaporation. The average number of neutrons emitted per fission (\nu) is generally comparable to or slightly lower than in neutron-induced fission for similar isotopes, reflecting the lower initial excitation energy available in the spontaneous case. For ^{238}\mathrm{U}, \nu \approx 2.0, in contrast to \nu \approx 2.4 for thermal neutron-induced fission of ^{235}\mathrm{U}.^[40] The fission mass distribution is predominantly asymmetric for actinides like uranium, leading to neutron energy spectra that resemble those from induced fission but with a reduced tail of high-energy neutrons due to the absence of additional excitation from the incident particle.^[42] Key isotopes exhibiting significant spontaneous fission include californium-252 (^{252}\mathrm{Cf}) and plutonium-244 (^{244}\mathrm{Pu}). For ^{252}\mathrm{Cf}, the spontaneous fission half-life is 85.8 years, with \nu \approx 3.76, making it a prolific neutron emitter at rates of about $2.3 \times 10^{12} neutrons per second per gram.^[40] This isotope is routinely employed as a calibration source for neutron detectors and in neutron radiography applications. Similarly, ^{244}\mathrm{Pu} has a spontaneous fission half-life of approximately $6.7 \times 10^{10} years, contributing to low-level neutron backgrounds in geological and cosmic studies.^[43] In neutrino experiments like KamLAND, spontaneous fission from trace actinides such as ^{238}\mathrm{U} in detector materials generates a minor but measurable neutron background, estimated at a few events per year above typical energy thresholds. Theoretical descriptions of spontaneous fission rely on the liquid drop model, which treats the nucleus as an incompressible fluid to estimate the fission barrier height B_f. For heavy actinides like ^{238}\mathrm{U}, the model predicts B_f \approx 5.8 MeV, augmented by shell corrections to match experimental half-lives; this barrier governs the tunneling action integral and thus the decay rate.^[44] More refined macroscopic-microscopic approaches incorporate proximity effects and asymmetry to better reproduce observed branching ratios and half-lives across the actinide region.^[45]

Photoneutron Emission

Mechanisms and Thresholds

Photoneutron emission, also known as the (γ, n) reaction, occurs when a nucleus absorbs a photon with sufficient energy to overcome the neutron separation energy S_n, leading to the ejection of a neutron and excitation primarily through the giant dipole resonance (GDR). The process requires the incident photon energy E_\gamma to exceed the threshold energy, typically around 8-10 MeV for most nuclei, as this energy range aligns with the GDR where collective oscillations of protons against neutrons facilitate neutron ejection.^[46] The threshold energy E_{th} accounts for the neutron separation energy and the recoil of the residual nucleus, given by the formula E_{th} = S_n \left(1 + \frac{m_n}{A-1}\right), where m_n is the neutron mass and A is the mass number of the target nucleus; for example, ^{93}\mathrm{Nb} has E_{th} \approx 8.07 MeV.^[46] This kinematic correction becomes more pronounced for lighter nuclei, such as deuterium with a lower threshold of 2.22 MeV due to its small S_n.^[46] The cross-section \sigma(E_\gamma) for the (γ, n) reaction exhibits a characteristic peak in the 10-30 MeV range associated with the GDR, reaching maximum values of 100-500 mb for various nuclei, before falling off at energies above 20 MeV as higher excitation modes dominate.^[46] For heavier nuclei, multiple neutron emission channels like (γ, 2n) open above approximately 18 MeV, where the cumulative separation energies allow sequential evaporation.^[46] In quantum terms, the reaction is driven by electric dipole (E1) photon absorption, which excites the nucleus to a GDR state, followed by statistical decay through neutron evaporation modeled by compound nucleus or preequilibrium processes.^[46]

Experimental and Astrophysical Contexts

Laboratory experiments on photoneutron emission primarily utilize electron accelerators to generate bremsstrahlung photon beams, enabling precise measurements of (γ,n) reaction cross-sections on various target nuclei. For instance, the High Intensity γ-ray Source (HIγS) at the Triangle Universities Nuclear Laboratory (TUNL) employs a free-electron laser to produce quasi-monoenergetic photons via inverse Compton scattering or bremsstrahlung, facilitating high-resolution studies of photoneutron yields from isotopes like ^{94}Mo and ^{90}Zr up to energies around 20 MeV. Activation foil techniques complement these setups by capturing emitted neutrons, which induce radioactivity in detector foils such as gold or indium; subsequent γ-ray spectroscopy of the activated foils quantifies neutron yields and spectra, offering a passive method robust against high photon backgrounds. Measurements on natural molybdenum targets for producing ^{99}Mo, used in diagnostic imaging, were conducted at the Electron Linear Accelerator with Bremsstrahlung (ELBE) facility at Helmholtz-Zentrum Dresden-Rossendorf (HZDR) using superconducting electron beams up to 40 MeV. These 2016 experiments provided data on (γ,n) reactions near thresholds, including cross-sections for natMo(γ,xn) leading to ^{99}Mo, improving models for isotope production yields.^[47]^[48] In astrophysical contexts, photoneutron emission plays a crucial role in nucleosynthesis pathways, particularly as the reverse process of radiative neutron capture. During the slow neutron-capture process (s-process) in asymptotic giant branch stars, photoneutrons emitted via (γ,n) reactions counteract (n,γ) captures on unstable branch-point nuclei, influencing isotopic abundance ratios; for example, measurements on neodymium and samarium isotopes constrain γ-ray strength functions that model these equilibria, aiding in the reproduction of observed solar system abundances. In core-collapse supernovae, intense γ-ray fields from α-capture reactions and other explosive processes induce photoneutron emission, which competes with neutron captures to shape the path of the rapid neutron-capture process (r-process) for heavy element synthesis beyond the iron peak; recent studies as of 2024 on the neutron drip line further refine understanding of these (γ,n) effects in r-process dynamics.^[49] Studies of the giant dipole resonance (GDR) through photoneutron emission provide insights into nuclear structure, revealing collective excitations where protons oscillate against neutrons. Post-2010 experiments, such as those on ^{238}U and ^{232}Th using bremsstrahlung beams, have measured GDR parameters like width and centroid energy, probing isovector modes and deformation effects in actinides with improved resolution via neutron multiplicity sorting. These findings update nuclear models, essential for understanding fission barriers and astrophysical reaction rates. Detection in both laboratory and astrophysical simulations relies on neutron time-of-flight (TOF) spectrometers, which determine neutron energies from flight times over known distances to scintillation detectors, achieving resolutions down to keV for spectra up to 20 MeV.^[50] Cosmic ray-induced backgrounds pose challenges, producing secondary neutrons that mimic photoneutrons; shielding with lead or polyethylene and coincidence gating reduce these interferences, ensuring signal purity in low-flux environments.^[51]

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[PDF] MEASURED AND CALCULATED EFFECTIVE DELAYED ...
The effective total delayed neutron fraction is designated βeff. The value of this parameter for a given fuel will vary over the lifetime of the reactor core, ...
[32]
[PDF] detecting, locating and identifying failed fuel in canadian power ...
Failed fuel is detected by monitoring coolant for fission products and radioiodines. Location is done on-power by delayed neutron monitoring, or off-power by ...
[33]
Physics of Uranium and Nuclear Energy
May 16, 2025 · Activation products in a reactor (and particularly its steel components exposed to neutrons) range from tritium (H-3) and carbon-14, to cobalt- ...<|control11|><|separator|>
[34]
[PDF] induced fission of 235U(n , f) - IAEA-NDS
A good agreement is observed between average number of prompt neutrons obtained by this experiment and other authors. average prompt neutron multiplicity vs TKE ...
[35]
[PDF] Evaluation and Use of the Prompt Fission Neutron Spectrum and ...
Parameters (r,α) of Kornilov PFNS and parameters (a,b) of Watt model. Parameter U-235. U-238. Pu-239 r=T l. /T h. 1.1215±3.0% 1.248±3.1% 1.1215±3.0% α. 0.905± ...
[36]
Full article: Energy dependent calculations of fission product, prompt ...
When an incident neutron energy goes higher, it is natural that ¯ 𝜈 p also increases monotonously, since the formed compound nucleus has larger available total ...
[37]
Neutron Multiplicity in the Fission of and with Neutrons up to 200 MeV
Feb 11, 2005 · The main feature is the dependence of the average total fission-fragment kinetic energy and the average gamma energy on neutron incident energy.Abstract · Comments & Replies · Article Text
[38]
The LANL/LLNL Prompt Fission Neutron Spectrum Program at ...
Neutrons from the WNR/LANSCE neutron source are being used to induce fission in a Parallel-Plate Avalanche Counter (PPAC). Two arrays of neutron detectors are ...
[39]
[PDF] 1. Spontaneous Fission Neutron Yields - IAEA Nuclear Data Services
Mar 13, 2015 · The currently available nuclear data relevant to the spontaneous fission neutron yields are presented in Table 1. The Total Half-lives were ...Missing: 252Cf | Show results with:252Cf
[40]
Microscopic Theory for Spontaneous Fission - Frontiers
Oct 28, 2020 · In the SF process, a fissioning nucleus undergoes quantum tunneling through a single or multiple potential barriers generated by the coherent ...
[41]
Spontaneous Fission | Definition & Theory | nuclear-power.com
Similarly, as for alpha decay, spontaneous fission occurs due to quantum tunneling. ... Cf (half-life 2.645 years, SF branch ratio about 3.1 percent) can be used ...Missing: mechanism branching
[42]
[PDF] BNL-NCS—36961 DE86 001744 BNL-NCS-36961 - OSTI
Table XXII Spontaneous Fission Half-life of 244pu. Pef. 116. 115. 117. Ti/a (1010 Years). 2.5 (0.8). 6.67 (0.32). 6.8 (0.8). 10. Page 11. c'uC. Reference.
[43]
[PDF] Lecture 10: Fission - INPP - Ohio University
Fission barrier height. • In a liquid drop estimate, the fission barrier height is the difference between the ground-state binding energy of a system and the ...
[44]
[PDF] Modern Fission Theory for Criticality
Reparametrizes the Frankel and Metropolis formula to reproduce the 238U spontaneous fission half-life. The coefficient for dependence on barrier height is ...
[45]
[PDF] +andbook on photonuclear data for applications Cross sections and ...
This handbook covers photonuclear data, describing interactions of photons with atomic nuclei, used in radiation shielding, radiotherapy, and inspection ...<|control11|><|separator|>
[46]
https://www-pub.iaea.org/MTCD/Publications/PDF/te_1178_prn.pdf
[47]
Photo-neutron reaction cross-sections for nat Mo in the ...
Jul 21, 2016 · The natMo( γ ,xn)90, 91, 99Mo reaction cross-sections were experimentally determined for the bremsstrahlung end-point energies of 12, 14, ...
[48]
Location of the neutron drip line for Sn and its impact on r-process ...
It is expected that the r-process occurs via a sequence of rapid neutron captures and photo-neutron emission reactions which produces unstable nuclei far on ...
[49]
Experimental study of photoneutron spectra from tantalum, tungsten ...
The neutron counting spectrum Y(E) was computed from the time of flight into the energy of neutron events with a light yield greater than the bias energy of ...
[50]
Measurements of cosmic ray induced background neutrons near the ...
This report documents measurements of cosmic ray induced background neutrons using a new Bonner sphere spectrometer (BSS) based on a 3He thermal neutron ...Missing: photoneutron | Show results with:photoneutron