Skip to main navigation Skip to search Skip to main content

Neutronics and safety studies on a research reactor concept for an advanced neutron source

  • Zeyun Wu
  • , Robert E. Williams
  • , J. Michael Rowe
  • , Thomas H. Newton
  • , Sean O'Kelly

Research output: Contribution to journalArticlepeer-review

22 Scopus citations

Abstract

This paper presents preliminary neutronics and thermal hydraulics safety analysis results for a low-enriched uranium (LEU) fueled research reactor concept being studied at the National Institute of Standards and Technology (NIST). The main goal of this research reactor is to provide advanced sources for neutron scattering experiments with a particular emphasis given to high intensity cold neutron sources (CNSs). A tank-in-pool type reactor with an innovative horizontally split compact core was developed in order to maximize the yield of the thermal flux trap in the reflector area. The reactor concept considered a 20 MW thermal power and a 30-day operating cycle. For non-proliferation purposes, a LEU fuel (U3Si2-Al) with 19.75 wt% enrichment was used. The core performance characteristics of an equilibrium cycle with several representative burnup states-including startup and end of cycle-were obtained using the Monte Carlo-based code MCNP6. The estimated maximum perturbed thermal flux of the core is ~5.0 × 1014 n/cm2-s. The calculated brightness of the CNS demonstrates an average gain factor of ~4 compared to the current source operated at the existing NIST reactor. Sufficient reactivity control worth and shutdown margins were provided by hafnium control elements. Reactivity coefficients were evaluated to ensure negative feedback. Thermal hydraulics safety studies of the reactor were performed using the multi-channel safety analysis code PARET. Steady-state analysis shows that the peak cladding temperature and minimum critical heat flux ratio are less than design limits with sufficient safety margins. Detailed transient analyses for a couple of hypothetical design-basis accidents show that no fuel damage or cladding failure would occur with the protection of reactor scrams. All these study results suggest this new research reactor concept offers a demonstrable potential to greatly expand the cold neutron capability with a 20 MW power and certified LEU fuels.

Original languageEnglish
Pages (from-to)67-82
Number of pages16
JournalNuclear Technology
Volume199
Issue number1
DOIs
StatePublished - Jul 2017

Keywords

  • Cold neutron source
  • Low-enriched uranium
  • Research reactor

Fingerprint

Dive into the research topics of 'Neutronics and safety studies on a research reactor concept for an advanced neutron source'. Together they form a unique fingerprint.

Cite this