This repository contains a working version of the thermal neutron reaction cross-section data table generated by the EXFOR parser.
- Each directory (
n-a
,n-el
,n-f
,n-g
,n-p
, andn-tot
) contains reaction cross-section data for the respective reactions: (n,a), (n,el), (n,f), (n,g), (n,p), and (n,total). These data are extracted from the EXFOR Master using the EXFOR parser. - The EXFOR data version used is v20250113.0.
- The incident neutron energy range is 0.0235 eV +/- 0.001 eV.
- The EXFOR data table includes the following columns:
- EXFOR ID: EXFOR entry number (5-digit) - subentry number (3-digit) - pointer number (1-digit), e.g.,
12345-002-0
. - First author: Name of the first author.
- Year: Year of publication.
- en_inc: Incident neutron energy.
- den_inc: Data error of the incident neutron energy.
- data: Cross-section in barns.
- ddata: Data error of the cross-section in barns.
- sf8: Reaction modifiers. See details for
Modifiers
in EXFOR dictionary - diction:34. - sf9: Data type. See details for
data types
difined in EXFOR dictionary diction:35.
- EXFOR ID: EXFOR entry number (5-digit) - subentry number (3-digit) - pointer number (1-digit), e.g.,
Clone the repository from a terminal using:
git clone https://github.com/shinokumura/thermaldata.git
Download from this link.
3-LI-6.txt (n,g)
# Header:
# title: 3-LI-6(N,G) thermal cross section
# source: EXFOR
# date created: 2025-01-22
# Target:
# Z: 3
# A: 6
# Nuclide: 3-LI-6
# Reaction:
# Type: N,G
# Incident energy : 2.5300e-08 MeV - 2.5300e-08 MeV
# Residual:
# Z: 3
# A: 7
# Nuclide: 3-LI-7
# Statistics:
# Thermal Simple Mean | Simple Stdev : 3.93000E-02 | NAN (N = 1)
# Thermal Weighted Mean +/- Weighted Error : NAN +/- NAN (N = 1)
# MXW Simple Mean | Simple Stdev : 4.80000E-02 | NAN (N = 1)
# MXW Weighted Mean +/- Weighted Error : NAN +/- NAN (N = 1)
# SPA Simple Mean | Simple Stdev : 3.47333E-02 | 5.84494E-03 (N = 3)
# SPA Weighted Mean +/- Weighted Error : 3.74321E-02 +/- 2.06736E-03 (N = 3)
#
# Data Table
# Experimental Data
# EXFOR ID First Author Year En_inc dEn_inc Data dData sf8 sf9
31768-023-0 R.B.Firestone 2016 2.5300E-08 0.0000E+00 3.9300E-02 7.0000E-04
22510-002-0 L.Jarczyk 1961 2.5300E-08 0.0000E+00 4.8000E-02 1.5000E-02 MXW
11014-002-0 G.A.Bartholomew 1957 2.5300E-08 0.0000E+00 2.8000E-02 8.0000E-03 SPA
13879-002-0 E.T.Jurney 1973 2.5300E-08 0.0000E+00 3.8500E-02 3.0000E-03 SPA
31570-003-0 Chang Su Park 2006 2.5300E-08 0.0000E+00 3.7700E-02 3.0537E-03 SPA
# ------------------
# Recom./Eval./Deriv./Calc. Data
# EXFOR ID First Author Year En_inc dEn_inc Data dData sf8 sf9
V1001-011-1 S.F.Mughabghab 2006 2.5300E-08 0.0000E+00 3.8500E-02 3.0000E-03 RECOM
# ------------------
#
The dataset was analyzed to calculate the mean and its associated uncertainty using the following methods:
-
Simple Mean ($ \mu $):
$ \mu = \frac{1}{N} \sum_{i=1}^N x_i $,where $ N $ is the total number of data points, and $ x_i $ is each data value. This value was obtained by pandas.DataFrame.mean.
-
Standard Deviation ($ \sigma $):
$ \sigma = \sqrt{\frac{1}{N-1} \sum_{i=1}^N (x_i - \mu)^2} $The standard deviation was also calculated by pandas.DataFrame.std.
For entries with valid errors ($ d_i > 0 $), the weighted mean and its uncertainty were calculated:
-
Weighted Mean ($ \mu_w $):
$ \mu_w = \frac{\sum_{i=1}^N w_i x_i}{\sum_{i=1}^N w_i} $ where $ w_i = \frac{1}{d_i^2} $ is the weight based on the inverse square of the error $ d_i $. -
Uncertainty of Weighted Mean ($ \sigma_w $):
$ \sigma_w = \sqrt{\frac{1}{\sum_{i=1}^N w_i}} $
- Dataset with zero uncertainty ($ d_i = 0 $) (where the original EXFOR entry does not have DATA-ERR) were excluded from the weighted calculations.
22 Jan., 2025 Shin