N →
Z ↓
Edges are inferred from the decay-mode fields in the bundled ground-state table. Curated metastable overrides are used where explicitly bundled.
t—
After an inventory calculation, the scrubber changes node weight by activity and labels decay edges with the instantaneous branch flow λN·b [s⁻¹] at the selected time.
| Nuclide | Amount | Unit |
|---|
Optional constant source terms — continuous production or feed in atoms/s. Source-only calculations are allowed.
| Nuclide | Source [atoms/s] |
|---|
Uncertainty at scrubber time — reported numerical half-life and branch uncertainties only.
General branching decay network: dN/dt = A·N + S. The browser evaluates the stiff Bateman/depletion system with 48th-order incomplete-partial-factorization CRAM. Resonance widths may act as transient intermediate rates, but cannot be entered as standalone inventories.
time—
Committed effective dose coefficients — import only. No coefficients are bundled. Keep age, route and chemical/absorption assumptions in the profile name. The current ICRP public-intake series reports committed effective dose per intake in Sv/Bq.
Accepted long form: nuclide, route, coefficient_Sv_per_Bq. Wide form is also accepted with ingestion_Sv_per_Bq and/or inhalation_Sv_per_Bq. Optional columns: profile, age, absorption_type, source. Duplicate nuclide/route/profile rows with conflicting values are rejected.
Import a provenance-qualified coefficient table. Missing coefficients remain unknown, not zero.
ICRP Dose Assessment Resources ↗ · ICRP Publication 158 ↗. These are reference links only; the tool performs no runtime network fetch.
Selected · ingestion—
Selected · inhalation—
Profile coverage—
Active profile / provenance
No data imported.
Cross-profile comparison
Import two or more profiles to compare age / chemical-form assumptions.
Inventory hypothetical complete-intake committed dose @ scrubber time
Run Inventory and import coefficients.
This is A(t) [Bq] × e [Sv/Bq] for a hypothetical intake of the entire current activity of each covered nuclide. It is not a dose rate and does not model release fraction, airborne concentration, breathing/ingestion rate, shielding or external exposure.
One target → one product, constant flux. Target radioactive decay, neutron-capture removal and product decay are included. (n,γ)/(n,2n) enforce Z,A consistency; use user-defined production for other channels. Enter a spectrum-appropriate one-group cross section.
Product atoms at EOI—
Activity at EOI—
Activity after cooling—
Load-following / restart schedule
First row must start at 0 h. Each row changes flux instantaneously and holds it until the next row. Times must be strictly increasing and within the simulation horizon.
The transfer converts concentrations [atoms/cm³] to atom counts using the reference volume. Inventory then assumes neutron flux = 0; use it for subsequent cooling/decay, not continued in-core burnup.
Model provenance. I-135 and Xe-135 half-lives come from this atlas data pack. Fission yields γI=0.0639, γX=0.00237, Xe-135 absorption σ=2.65×10⁶ b, Σf=0.0616 cm⁻¹ and ν=2.43 are inherited from the site’s dedicated xenon.html homogeneous model.
Equations: dI/dt = γIΣfφ − λII; dX/dt = γXΣfφ + λII − (λX+σaφ)X. A constant post-event flux is applied at t=0 and solved with CRAM48.
Initial Xe worth—
Maximum |Xe worth|—
Time of maximum—
Dead-time above margin—
Xe captures over horizon—
Xe β decays over horizon—
time—
Model boundary. These are collapsed cumulative chain-yield presets reused from decayheat.html. They approximate omitted upstream precursors by assigning cumulative yield to the highest explicitly modelled member of a reduced chain. They are not prompt independent yields and are not ENDF/B-VIII.1 data.
Four metastable products in the reduced preset are not present in this atlas data pack; ten generic short-lived FP heat buckets from decayheat.html are deliberately excluded because they have no nuclide identity.
Bundled evaluated FPY sets
Evaluated / custom FPY import
Import contract. Use dimensionless yield fraction per fission (0.06 = 6%), with optional 1σ uncertainty in the same units. Independent yields may seed the decay inventory. General cumulative evaluated yields are display-only here because seeding every cumulative product would double-count precursor feeding. In ENDF-6 terminology, MT 454 is independent FPY and MT 459 is cumulative FPY.
Fission irradiation · thin target
Boundary. Constant flux and one-group σ; target depletion includes fission, capture and radioactive decay. Product decay during irradiation is solved by CRAM48. Neutron reactions on fission products, self-shielding and spatial flux depression are omitted. Production-matrix transfer requires independent FPY.
→
Isotopes — same Z
Isobars — same A
Isotones — same N
Nuclide series explorer
Click a plotted point or a nuclide label to select it. Half-life and specific activity use logarithmic Y; stable nuclides have no finite half-life/specific-activity point.
Compare nuclides
Curve shows parent survival N(t)/N₀; it does not include daughter activity. Resonance-width states are excluded from this comparison.
Magic-number guides: N or Z = 2, 8, 20, 28, 50, 82, 126. Derived shell indicators use S₂ₙ(Z,N)=Sₙ(Z,N)+Sₙ(Z,N−1), S₂ₚ(Z,N)=Sₚ(Z,N)+Sₚ(Z−1,N), δ₂ₙ=S₂ₙ(Z,N)−S₂ₙ(Z,N+2), and δ₂ₚ=S₂ₚ(Z,N)−S₂ₚ(Z+2,N). The chart uses Z downward and N to the right.
Decay γ emissions for selected parent state
Quantitative source lines use bundled decay-radiation intensities. Empty means “not bundled”, not “no gamma emission”. Structural level-to-level transitions are a separate data concept and are not substituted for decay emission probability.
Decay-data layer coverage
Bundled data source
Known inventory γ-line spectrum @ scrubber time
Run an Inventory calculation to assemble the known line spectrum.
Partial line spectrum only: it sums the finite-energy, finite-intensity γ lines bundled in this atlas. Missing lines or nuclides are unknown, not zero.
FENDL-3.2c neutron cross sections · 293.6 K
Pointwise local FENDL-3.2c data are loaded on demand from neutron-data/. Ground states only.
Total—
Elastic—
Radiative capture (n,γ)—
Fission—
totalelasticcapturefission
σ̄ capture: —σ̄ fission: —
Flux weighting changes the neutron spectrum only; FENDL cross sections remain the 293.6 K pointwise base library.
The point curve is microscopic σ(E). Spectrum averages use logarithmic quadrature and are an interactive engineering approximation, not a replacement for evaluated multigroup processing.