MFE/ACT: A TRS-80 code for calculating neutron activation
Abstract
The MFE/ACT code, written to run on the TRS-80, can be used to calculate the neutron activation of materials used in fission and fusion reactors. Input data include the specific isotopes to be calculated, the neutron fluxes, the neutron cross sections, and the nuclear decay half-lives.
- Publication:
-
Unknown
- Pub Date:
- October 1982
- Bibcode:
- 1982mfe..rept.....D
- Keywords:
-
- Computer Programs;
- Neutron Activation Analysis;
- Neutron Irradiation;
- Radiation Effects;
- Reactor Materials;
- Input;
- Neutron Cross Sections;
- Nuclear Reactors;
- Output;
- Radioactive Isotopes;
- Atomic and Molecular Physics