Reference input spectra

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The collapsed cross-sections depend strongly on the nature of the projectile spectra, and so it is important to use the appropriate spectrum together with the appropriately-weighted cross-section data. With the advances of modern simulation software and high resolution spectra the user is reminded of the importance of the tails, low or high-energy ones, on the reaction rates.

The majority of neutron-application spectra stem from light-water assemblies, mock-ups or reactors where the integral responses are strongly, if not solely, influenced by the energy ranges of the fission spectra and thermal maxwellian. Fusion spectra that have been obtained from magnetic confinement (MCF) or inertial confinement fusion (ICF) present typical D-D 2.5 MeV, or D-T 14 MeV peaks sometimes accompanied by a higher-energy tail, but also showing rather different slowing-down profiles. Accelerator-driven beam spectra are important in their role in nuclear data acquisition and materials research, but also for medical therapeutic and diagnostic applications.

In essence the particle spectrum profile, through the collapsing process, emphasises the energy region of most importance for each application. Transferring data from one application or energy range to another should be done with great care as it can easily lead to misleading and inappropriate numerical results.

Several incident particle spectra are provided in the table below, mostly including neutron incident spectra but with some charged particle spectra. Note that these are provided in the original energy group structures as generated by the code(s) that calculated them. These are often not the same energy group structures as those provided for e.g. the TENDL nuclear data libraries and require a flux conversion using GRPCONVERT. Note that while the group conversion can easily be performed, this cannot add structure when moving to a refined group structure when moving to a more refined multi-group.

Each of the spectra below is provided in the format of an arbitrary flux arb_flux file for reading in the GRPCONVERT module as well as a figure showing the spectrum in flux per unit lethargy using an arbitrary normalisation. For convenience, all of the arb_flux files are available in the table below.


Reference incident particle spectra
Name Group Particle arb_flux file Figure Description
Bigten 407 n Media:407 Bigten.txt Bigten International Criticality Safety Benchmark Experiment, Bigten
BWR-MOX-Gd-0 1102 n Media:1102 BWR-MOX-Gd-0.txt BWR-MOX-Gd-0 BWR MOX fuel with Gd, 0 GWd/THM
BWR-MOX-Gd-15 1102 n Media:1102 BWR-MOX-Gd-15.txt BWR-MOX-Gd-15 BWR MOX fuel with Gd, 15 GWd/THM
BWR-MOX-Gd-40 1102 n Media:1102 BWR-MOX-Gd-40.txt BWR-MOX-Gd-40 BWR MOX fuel with Gd, 40 GWd/THM
BWR-RPV 198 n Media:198 BWR-RPV.txt BWR-RPV Boiling water reactor, 1/4 Thickness reactor pressure vessel
BWR-UO2-Gd-0 1102 n Media:1102 BWR-UO2-Gd-0.txt BWR-UO2-Gd-0 BWR UO2 fuel with Gd, 0 GWd/THM
BWR-UO2-Gd-15 1102 n Media:1102 BWR-UO2-Gd-15.txt BWR-UO2-Gd-15 BWR UO2 fuel with Gd, 15 GWd/THM
BWR-UO2-Gd-40 1102 n Media:1102 BWR-UO2-Gd-40.txt BWR-UO2-Gd-40 BWR UO2 fuel with Gd, 40 GWd/THM
CERN-H4IRRAD 288 n Media:288 CERN-H4IRRAD.txt CERN-H4IRRAD CERN H4IRRAD experiment
Cf252 070 n Media:070 Cf252.txt Cf252 Californium-252 spontaneous fission source
DEMO-HCPB-BP 616 n Media:616 DEMO-HCPB-BP.txt DEMO-HCPB-BP DEMO fusion concept He-cooled pebble bed, backplate
DEMO-HCPB-FW 616 n Media:616 DEMO-HCPB-FW.txt DEMO-HCPB-FW DEMO fusion concept He-cooled pebble bed, first wall
DEMO-HCPB-VV 616 n Media:616 DEMO-HCPB-VV.txt DEMO-HCPB-VV DEMO fusion concept He-cooled pebble bed, vacuum vessel
EBR-2 029 n Media:029 EBR-2.txt EBR-2 Experimental Breeder Reactor spectrum
Frascati-NG 175 n Media:175 Frascati-NG.txt Frascati-NG ENEA Frascati Neutron Generator D-T
HCLL-FW 616 n Media:616 HCLL-FW.txt HCLL-FW D-T fusion reactor He-cooled LiPb, first wall
HCLL-VV 616 n Media:616 HCLL-VV.txt HCLL-VV D-T fusion reactor He-cooled LiPb, vacuum vessel
HCPB-FW 616 n Media:616 HCPB-FW.txt HCPB-FW D-T fusion reactor He-cooled pebble bed, first wall
HCPB-VV 616 n Media:616 HCPB-VV.txt HCPB-VV D-T fusion reactor He-cooled pebble bed, vacuum vessel
HFIR-highres 238 n Media:238 HFIR-highres.txt HFIR-highres Material test reactor, Oak Ridge HFIR midplane
HFIR-lowres 100 n Media:100 HFIR-lowres.txt HFIR-lowres Material test reactor, Oak Ridge HFIR midplane
HFIR-VXF3-AD 238 n Media:238 HFIR-VXF3-AD.txt HFIR-VXF3-AD Material test reactor, Oak Ridge HFIR midplane-VXF3-AD
HFR-high 616 n Media:616 HFR-high.txt HFR-high Material test reactor, Petten HFR high
HFR-low 616 n Media:616 HFR-low.txt HFR-low Material test reactor, Petten HFR low
IFMIF-DLi 211 n Media:211 IFMIF-DLi.txt IFMIF-DLi IFMIF D-Li neutron source
ITER-DD 175 n Media:175 ITER-DD.txt ITER-DD Magnetic confinement fusion, ITER D-D
ITER-DT 175 n Media:175 ITER-DT.txt ITER-DT Magnetic confinement fusion, ITER D-T
JAEA-FNS 175 n Media:175 JAEA-FNS.txt JAEA-FNS JAEA Fusion Neutron Source D-T
JET-FW 100 n Media:100 JET-FW.txt JET-FW Joint European Torus, first wall vacuum vessel
LMJ-g 161 γ Media:161 LMJ-g.txt LMJ-g Laser Mégajoule gamma spectra
Maxwellians 709 n 1 keV 5 keV 10 keV 30 keV 80 keV Maxwellians Maxwellian neutron spectra at various temperatures
NIF-ignition 150 n Media:150 NIF-ignition.txt NIF-ignition Inertial confinement fusion, NIF ignited
Paluel 172 n Media:172 Paluel.txt Paluel Paluel light water reactor
Phenix 172 n Media:172 Phenix.txt Phenix Fast breeder reactor, Phénix
PWR-MOX-0 1102 n Media:1102 PWR-MOX-0.txt PWR-MOX-0 PWR MOX fuel with Gd, 0 GWd/THM
PWR-MOX-15 1102 n Media:1102 PWR-MOX-15.txt PWR-MOX-15 PWR MOX fuel with Gd, 15 GWd/THM
PWR-MOX-40 1102 n Media:1102 PWR-MOX-40.txt PWR-MOX-40 PWR MOX fuel with Gd, 40 GWd/THM
PWR-RPV 198 n Media:198 PWR-RPV.txt PWR-RPV Pressurized water reactor, 1/4 Thickness reactor pressure vessel
PWR-UO2-0 1102 n Media:1102 PWR-UO2-0.txt PWR-UO2-0 PWR UO2 fuel, 0 GWd/THM
PWR-UO2-15 1102 n Media:1102 PWR-UO2-15.txt PWR-UO2-15 PWR UO2 fuel, 15 GWd/THM
PWR-UO2-40 1102 n Media:1102 PWR-UO2-40.txt PWR-UO2-40 PWR UO2 fuel, 40 GWd/THM
PWR-UO2-Gd-0 1102 n Media:1102 PWR-UO2-Gd-0.txt PWR-UO2-Gd-0 PWR UO2 fuel with Gd, 0 GWd/THM
PWR-UO2-Gd-15 1102 n Media:1102 PWR-UO2-Gd-15.txt PWR-UO2-Gd-15 PWR UO2 fuel with Gd, 15 GWd/THM
PWR-UO2-Gd-40 1102 n Media:1102 PWR-UO2-Gd-40.txt PWR-UO2-Gd-40 PWR UO2 fuel with Gd, 40 GWd/THM
Superphenix 172 n Media:172 Superphenix.txt Superphenix Fast breeder reactor, Superphénix
TUD-NG 175 n Media:175 TUD-NG.txt TUD-NG TU Dresden fusion neutron source D-T
WCCB-FW 616 n Media:616 WCCB-FW.txt WCCB-FW D-T fusion water-cooled ceramic breeder, first wall
WCCB-VV 616 n Media:616 WCCB-VV.txt WCCB-VV D-T fusion water-cooled ceramic breeder, vacuum vessel
WCLL-FW 616 n Media:616 WCLL-FW.txt WCLL-FW D-T fusion water-cooled LiPb, first wall
WCLL-VV 616 n Media:616 WCLL-VV.txt WCLL-VV D-T fusion water-cooled LiPb, vacuum vessel


Bigten

BWR-MOX-Gd-0

BWR-MOX-Gd-15

BWR-MOX-Gd-40

BWR-RPV

BWR-UO2-Gd-0

BWR-UO2-Gd-15

BWR-UO2-Gd-40

CERN-H4IRRAD

Cf252

DEMO-HCPB-BP

DEMO-HCPB-FW

DEMO-HCPB-VV

EBR-2

Frascati-NG

HCLL-FW

HCLL-VV

HCPB-FW

HCPB-VV

HFIR-highres

HFIR-lowres

HFIR-VXF3-AD

HFR-high

HFR-low

IFMIF-DLi

ITER-DD

ITER-DT

JAEA-FNS

JET-FW

LMJ-g

Maxwellians

NIF-ignition

Paluel

Phenix

PWR-MOX-0

PWR-MOX-15

PWR-MOX-40

PWR-RPV

PWR-UO2-0

PWR-UO2-15

PWR-UO2-40

PWR-UO2-Gd-0

PWR-UO2-Gd-15

PWR-UO2-Gd-40

Superphenix

TUD-NG

WCCB-FW

WCCB-VV

WCLL-FW

WCLL-VV