The Neutron Metrology File (NMF-90) [1,2] is an integrated database for performing neutron spectrum adjustment (unfolding) calculations. It contains 4 different adjustment codes, the dosimetry  reaction cross section library IRDF-90/NMF-G with covariance files, 6 input data sets for reactor benchmark neutron fields and a number of utility codes for processing and plotting the input and output data.  

NMF-90 is divided into following modules: 
 

Module:	Click below to download compressed disk images:
DEMO	disk1, disk2
IRDF-90/NMF-G	disk3
STAYNL	disk4, disk5, disk6, disk7
MIEKE	disk8, disk9

Installation: downloaded disk images have to be uncompressed (e.g. with WinZip) and copied onto diskettes. Then, follow Install and Readme files contained on these diskettes (some of the files still will have to be   uncompressed). About 10 Mb of disk space is needed to install and run a typical reactor neutron dosimetry unfolding problem.  

Contents: 

 
• DEMO module contains a sample  problem  and   its solution with all the programs involved in the  NMF-90  (DEMO),   furthermore,  reference  data  sets  for   the benchmark neutron fields of the REAL-88 exercise.
• IRDF-90 module contains the cross section library (IRDF-90/NMF-G).
• STANYL, MIEKE, and LSL modules contain software    packages   and  utility  programs  for  neutron   spectrum adjustment  and  subsequent  radiation  damage   exposure   parameter    calculations. 

Each of these modules provides a complete neutron metrology calculation for radiation damage purposes: they start with cross section data processing (except LSL), perform neutron spectrum adjustment by the generalized least squares method and terminate in radiation damage exposure parameter calculation. 
The cross section library IRDF-90/NMF-G included as a separate module in NMF-90 is applied by the modules STAYNL and MIEKE. The program LSL has its own master library based on IRDF-85 data. 
The modules STAYNL and LSL have been written in standard Fortran77. The module MIEKE applies Microsoft Fortran77 compiler specific extensions, therefore, it can run only in that case if Microsoft run-time libraries are available. Mathematical coprocessor is strongly recommended.

The  subdirectory  REFS (on disk1) contains   consistent  data  sets (calculated  input  spectra  and   measured  reaction rates together with  their covariance information, and weighting  spectra  in  fine energy  group  structure) for neutron spectrum adjustment  in  six  different  spectrum cases: 

 
• ANO  Pressure vessel cavity of the Arkansas Power and Light         Reactor (Arkansas Nuclear One-1),
• PS1  Oak Ridge Research Reactor, Pool Side Facility in the metallurgical irradiation experiment (simulated surveillance  capsule),
• PS2  Oak Ridge Research Reactor, Pool Side Facility in the metallurgical irradiation experiment (T position in the simulated pressure vessel wall),
• U35  fission spectrum of the U-235,
• CFR  neutron spectrum in the center of the Coupled Fast Reactivity Measurement Facility (CFRMF),
• RTN  fusion simulation spectrum measured at the RTNS-II, a 14 MeV neutron source at the Lawrence Livermore Laboratory.

REFERENCES

1. E.J. Szondi, "The Group Version of the International Reactor Dosimetry File IRDF-90 for Use in the Neutron Metrology File NMF-90 (IRDF-90/NMF-G)", Report INDC(HUN)-34, Vienna, 1999. (PDF,33 KB)

2. E.M. Zsolnay, E.J. Szondi, H.J. Nolthenius, "The Neutron Metrology File NMF-90", Report IAEA-NDS-171, Rev. 1, Vienna, 1999. (PDF, 34KB).