3. FAST NEUTRON REACTION DATA ^[*]

The status of available neutron reaction data is published regularly in the CINDA (Computer Index of Neutron Data) series. CINDA (see, e.g., CINDA 2003) contains bibliographical references to measurements, calculations, reviews and evaluations of neutron cross sections and other microscopic nuclear data. It also includes index references to computer libraries of numerical neutron data available from regional nuclear data centers, such as the International Atomic Energy Agency's Nuclear Data Section (IAEA 2003), the OECD Nuclear Energy Agency's Data Bank (NEA 2003), the US National Nuclear Data Center (NNDC 2003), and the Russian Nuclear Data Center (RNDC 2003). Though the CINDA bibliography allows the users to find the references to specific types of cross-section information on neutron-induced reactions, recommended numerical data are indispensable in real applications.

The major fields of application of neutron data, in addition to nuclear theory, are as follows (Csikai 1987): fission reactor technology, fast-reactor design and control calculations, shielding calculations, radiation damage, neutron flux/fluence monitoring, fusion reactor technology, safeguards, neutron therapy, medical physics, activation analysis, prompt radiation analysis, radionuclide production, transmutation of radioactive waste, radiobiology, nuclear geophysics, earth sciences, dosimetry, space sciences and nuclear astrophysics. Hundreds of requests exist for data at neutron energies up to 20 MeV, with an emphasis on 14 MeV neutrons produced in the ³H(d, n) ⁴He (D-T) reaction. In some cases, however, to avoid the disturbing effects of interfering reactions and gamma-lines the use of ²H(d, n) ³He (D-D)...