Published December 2019 | Version v1
Journal article

Computational study of full-scale VHTR lower plenum for turbulent mixing assessment☆

  • 1. Texas A&M University, Department of Nuclear Engineering, AIEN M104, 3133 TAMU, College Station, TX 77843 (United States)
  • 2. Texas A&M University, Institute of Scientific Computing, BLOC 619, 3404 TAMU, College Station, TX 77843 (United States)
  • 3. Texas A&M University, Department of Nuclear Engineering, Department of Mechanical Engineering, AIEN 205D, 3133 TAMU, College Station, TX 77843 (United States)

Description

Highlights: • CFD is completed for lower plenum of a very-high-temperature reactor. • Unit cell is further analyzed consisting of six jets and seven support pedestals. • Approach velocity and temperature is quantified for three lower plenum locations. • Thermal stratification and non-uniformity are quantified for key locations. • Data is provided to aid future experimentalists to design scaled testbeds. - Abstract: Next-generation nuclear reactors are poised to efficiently provide reliable power at enhanced safety levels for many years to come. Among the fundamental designs for these reactors is the very-high-temperature reactor (VHTR), which employs helium as the primary coolant and has the potential of reaching elevated temperatures such that chemical processing (e.g., electrolysis for hydrogen production) is viable alongside traditional electricity generation. This and other next-generation reactors also represent a strategic bridge for ultimately transitioning from fossil fuel-dominated energy portfolios to one where renewable options abound. For the VHTR, the ultimate goal of constructing a new plant will be preceded by additional fundamental research aimed at generating trusted models for behavior prediction under normal and accident scenarios. This paper presents a detailed computational fluid dynamics simulation of the lower plenum, where hot coolant from the core mixes together in a turbulent fashion before traveling to power conversion equipment. Because the flow is expected to enter the lower plenum across a wide range of temperatures and velocities, concerns exist when the mixing is incomplete. The potential hot spots on cylindrical support pedestals and the uniformity of the main outlet are the primary metrics of interest in this study, along with flow velocities and temperatures at different locations within the lower plenum. Three locations are probed in detail and suggest a large range exists for approach velocities and temperatures. A large degree of stratification is also seen on the surfaces of the support pedestals, suggesting a facility should accommodate testing for such behavior. The characterizations presented provide the valuable data needed in order to design appropriate experimental testbeds, where scaled modeling can be carried out in a manner meaningful in predicting the full-scale behavior.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2019.05.055

Additional details

Identifiers

DOI
10.1016/j.anucene.2019.05.055;
PII
S0306454919303081;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
134
Journal Page Range
p. 101-113
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Notes
© 2019 Elsevier Ltd. All rights reserved.