Published April 2018 | Version v1
Journal article

The IAEA CRP on HTGR uncertainties: Sensitivity study of PHISICS/RELAP5-3D MHTGR-350 core calculations using various SCALE/NEWT cross-section sets for Ex. II-1a

  • 1. Nuclear Engineering Department, The North Carolina State University, 2500 Stinson Drive, Raleigh, NC 27606 (United States)
  • 2. Nuclear Science and Engineering Division, The Idaho National Laboratory, 2525 N. Fremont Ave, Idaho Falls, ID 83415 (United States)

Description

Uncertainty and sensitivity analysis is an indispensable element of any substantial attempt in reactor simulation validation. A Coordinated Research Program (CRP) supervised by the International Atomic Energy Agency was started to investigate the various uncertainty quantification methodologies for High Temperature Gas-cooled Reactors. The first phase of the CRP is dedicated to the estimation of cell and lattice model uncertainties due to the neutron cross sections. Phase II is oriented towards the investigation of propagated uncertainties from the lattice to the coupled neutronics/thermal hydraulics core calculations. Best-estimate results for the prismatic single block (Ex. I-2a) and super cell models (Ex. I-2c) were obtained using the SCALE 6.2.0 two-dimensional lattice code NEWT. A reference spectrum was obtained with Serpent 2.1.27 for the single block, super cell and core models. The flux spectrum in the system of interest plays a primary role in the quantification of uncertainties caused by cross sections. In this work, the TRITON/NEWT-flux-weighted cross sections obtained for Ex. I-2a and various models of Ex.I-2c are utilized to perform a sensitivity analysis of the MHTGR-350 core power densities and eigenvalues. The core solutions are obtained with the Idaho National Laboratory (INL) coupled code PHISICS/RELAP5-3D. It is observed that axial shape of the core power density does not vary significantly with the various lattice cell libraries utilized. The use of cross section libraries originating from super cells induces changes of the core power density by 1–10% radially as compared to the Ex.I-2a cross sections. The magnitude of these variations increases as the moderator-to-fuel ratio increases in the super cell lattice models. A lattice flux spectrum resembling the core spectrum is hence necessary for correct predictions in nodal core calculations.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2017.12.008

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2017.12.008;
PII
S0029549317305800;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
329
Journal Page Range
p. 156-166
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
8. Topical Meeting on High Temperature Reactor Technology
Acronym
HTR 2016
Dates
6-10 Nov 2016
Place
Las Vegas, NV (United States)

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.