Uncertainty quantification in (α,n) neutron source calculations for an oxide matrix

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

IVG.1M is a research pressurized water reactor designed to use high-enriched fuel. As part of the core conversion program, the reactor will be switched to a new low-enriched composite uranium fuel. Further operation of the reactor is determined by the availability of fresh fuel to replace the core after the next campaign and the possibility of ensuring safe storage of irradiated spent nuclear fuel (SNF) unloaded from the core. The SNF storage conditions are assessed in terms of ensuring nuclear and radiation safety.

Radiation safety of the research reactor fuel storage is achieved, first of all, by solving problems of protection against γ-radiation, while neutron radiation, as a rule, is not considered due to its significantly lower intensity compared to γ-radiation. As for the new low-enriched fuel of the IVG.1M reactor, which is characterized by a set of elements with low and medium atomic masses, on which the (α, n) reaction is possible, the assessment of the neutron component is a necessary procedure to ensure safe fuel storage.

The authors of the article propose a procedure for calculating the neutron component of the radiation characteristics of fresh and irradiated composite fuel of the IVG.1M reactor, and also estimate the (α, n)-component. The results of the research will be useful in selecting SNF storage and transportation technologies as well as in providing scientific justification for the possibility of using neutron radiation to control burnup.

The research was carried out using verified computational codes MCNP5 and Sources-4C, high-precision experimental EXFOR and computational ENDSF data, as well as evaluated nuclear data libraries.

Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel

Safe irradiated nuclear fuel (INF) storage of research reactors is ensured by solving issues of protection against γ-irradiation while the neutron component is usually without consideration due to significantly lower intensity. Regarding the low-enriched composite uranium fuel of the IVG.1M reactor that is characterized by a set of elements with low and mean atomic weight where reaction is possible (α, n), evaluation of the neutron component is an indispensable procedure for ensuring radiation safety INF storage. This research suggests a method for neutron component calculation of radiation properties of fresh and irradiated fuel of the IVG.1M reactor, the α-n-component was evaluated. The research results will be useful when choosing a technology for INF storage and for analysis of feasibility to use neutron irradiation with a purpose to control fuel burnout.