EXFOR Plot File (CX4)

The EXFOR Plot File is the EXFOR Entry File converted to the CX4 (Compact EXFOR) format via the EXFOR JSON File (J4) by the ForEXy package [1]. The CX4 format has ($x, \Delta x, y, \Delta y$) structure, and its table structure is suitable for plotting. Each CX4 file is provided with a sample plot pdf file. See [2] for the original EXFOR Library.

Download

• download individual files of the current version from the EXFOR Plot File website, or
• download the full repository of the current version by using the terminal command:

git clone https://github.com/iaea-nds/exfor-plot-file.git

Directory structure

    +--+--x4_makcxl.log   # update log file
       +--x4_makcxl.txt   # index file
       |
       +--cx4
          |
          +--0            # spantaneous fissoin
          |  |
          |  +--Bk249       # Bk249(sf)
          |  ...
          |
          +--Ac215        # Ac-215 induced reaction
          ...
          +--a            # alpha-particle induced reactoin
          |  |
          |  +--Ag          # Ag+a
          |     |
          |     +--el         # Ag(a,a0)
          |        |
          |        +--adxc      # Ag(a,a0) dsigma/dOmega(cm)
          |        |  +--a-Ag-..._F0700.004.1.cx4 # EXFOR F0700.004.1 (CX4)
          |        |  +--a-Ag-..._F0700.004.1.pdf # EXFOR F0700.004.1 (PDF)
          |        |  +--a-Ag-..._F0700.004.2.cx4 # EXFOR F0700.004.2 (CX4)
          |        |  +--a-Ag-..._F0700.004.2.pdf # EXFOR F0700.004.2 (PDF)
          |        |  ...
          |        |
          |        +--adxl      # Ag(a,a0) dsigma/dOmega(lab)
          |           +--a-Ag-..._F1116.002.cx4 # EXFOR F1116.002 (CX4)
          |           +--a-Ag-..._F1116.002.pdf # EXFOR F1116.002 (PDF)
          ...
         

Contents

The following quantities are within the scope of these libraries:

• cross section (incl. gamma production)
• angular differential cross section (incl. gamma production)
• energy differential cross section (incl. gamma production)
• double differential cross section
• fission neutron multiplicity
• fission product yield

for any projectiles and reactions not leaving two or more heavy (A>4) nuclides.

Experimental data in

• 4 columns (x,dx,y,dy) for a dataset as a function of the

  • incident energy (excation function - "excfun"),
  • outgoing angle (angular distribution - "angdisc" and "angdisl"),
  • outgoing energy (energy distribution - "enedisc" and "enedisl"), or
  • level energy (level distribution - "lvldis")

• 3 columns (x,y,dy) for a dataset as a function of the

  • product nuclide (nuclide distirbution - "nucdis") N.B. the nuclide is give as a real number (e.g., 46109.9 for 109Pd).

• 2 columns (y,dy) for

  • neutron multiplicities for spontaneous fissions ("sponnu").

CX4 files are stroed in the following directory structure: $projectile/$target/$reaction/$quantity

Examples

• a/Ni/x/sig/a-Ni-x-sig-excfun-mon-prodCu64_Takacs_2020_D4408.005.cx4: Ni(a,x)64Cu production cross section as a function of the incident energy (excfun), published by Takacs in 2020 and compiled in EXFOR D4408.005.

• n/Fe56/el/adxc/n-Fe56-el-adxc-angdisc-mon-einc5.050E+06_prodFe56_Boschung_1971_10037.024.cx4: 56Fe(n,n0)56Fe angular differential cross sections in the c.m. system (adxc) at the incident energy (einc) of 5.05 MeV as a function of the c.m. angle (angdisc), published by Boschung in 1971 and compiled in EXFOR 10037.024.

• p/Bi209/xn/ddxl/p-Bi209-xn-ddxl-enedisl-mon-einc9.000E+07_angl20_Kalend_1983_C0841.008.cx4: 209Bi(p,n+x) double differential cross section in the lab. system (ddxl) at the incident energy (einc) of 90 MeV and outgoing angle in the lab. system (angl) at 20 deg as a function of the outgoing neutron energy in the lab. system (enedisl), published by Kalend in 1983 and compiled in EXFOR C0841.008.

Abbreviations in CX4 file names

Isomeric state

An isomeric state is indicated by

• g: ground state production (G)
• m: first metastable state production (M or M1)
• n: second metastable state production (M2)
• p: ground + first metastable state production (G+M1)
• q: ground + second metastable state production (G+M2)
• r: first + second metastable state production (M1+M2)

Example "Au196n" is for 196m2Au (9.6 h) while "Au196p" is for the sum of 196gAu (6.2 d) and 196g1Au (8.1 s).

Physical quantity

• adxc: angular differential cross section in c.m. system
• adxl: angular differential cross section in lab. system
• ddxc: double differential cross section in c.m. system
• ddxl: double differential cross section in lab. system
• edxc: energy differential cross seciton in c.m. system
• edxl: energy differential cross seciton in lab. system
• sig: cross section
• sigc: cross section (cumulative)
• fyc: fission product yield (cumulative)
• fyi: fission product yield (independent)
• nud: fission neutron multiplicity (delayed)
• nup: fission neutron multiplicity (prompt)
• nut: fission neutron multiplicity (total)

Distribution (running variable)

• angdisc: c.m. angle dependence
• angdisl: lab. angle dependence
• enedisc: c.m. outgoing energy dependence
• enedisl: lab. outgoing energy dependence
• excfun: incident energy dependence
• lvldis: level energy dependence
• nucdis: product nuclide dependence
• othdis: other distribution (probably indication of processing error!)
• sponnu: spontaneous fission neutron multiplicity

Incident particle spectrum

• brs: bremsstrahlung spectrum average and unfolded
• fis: fission neutron spectrum field
• mon: mono energetic field
• mxw: Maxwellian field
• sdt: slow-down time spectrometer field
• spa: averaged over a spectrum with ~0.0253 eV or narrow energy width

Constant

• angc: c.m. angle
• angl: lab. angle
• elvl: excitation energy (of product)
• enec: c.m. outgoing energy
• enel: lab. outgoing energy
• prod: product

Author name

A blank and "-" in author's name are replaced by "%" and "+" in the file name (e.g., "Abd%El+Kariem" for "Abd El-Kariem".)

References

1. N. Otuka, V. Devi, O. Iwamoto, Appl. Radiat. Isot. 225 (2025) 111903 [pdf].
2. N. Otuka et al., Nucl. Data Sheets 120 (2014) 272 [pdf].