Energy deposition in coolant of PWR under normal operation and accident conditions
Creators
- 1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)
- 2. Nuclear Research Center – Negev, P.O. Box 9001, 84190 Beer-Sheva (Israel)
- 3. DES, Service d'études des réacteurs et de mathématiques appliquées (SERMA), CEA, Université Paris-Saclay, F-91191 Gif-sur-Yvette (France)
Description
Highlights: • Energy deposition in the cooolant of PWR by neutron and photon particles is studied. • Coolant heating is calculated by coupled neutron-photon calculations with OpenMC. • A representative fuel pin cell problem is calculated under different physical conditions, covering normal operation and accidental transients. • A correlation on pure water density and boron concentration is presented for fast prediction of coolant heating. In reactor core analysis, the energy deposition in the coolant is often regarded as a fixed amount. In this work we study the validity of this assumption at normal operation and under accident conditions in PWR. A fuel pin cell and other lattice elements from the VERA benchmark's 2-D fuel assemblies are used to calculate photon and neutron energy deposition in the coolant by OpenMC. The adoption of a subcooled-boiling model for the coolant with non-uniform void fraction in the sub-channel is taken into account, without revealing however significant differences on the reaction rates used to score the coolant heating. Specifically, we study the effects of void fraction, pressure and coolant temperature on deposited energy. Chemical shim operated by diluted boric acid in water is also considered. Results show that coolant heating fraction can change significantly under accident conditions. Moreover, it can be expressed as a function of pure water density and boron concentration, where water is always considered as a homogeneous mixture also in presence of two-phase flow. Specifically, we provide a correlation fitting the numerical results from OpenMC pin cell calculations by least squares regression, in order to predict energy deposition in the coolant of the subchannels present in a fuel lattice. This correlation is explicitly intended for implementation in thermal–hydraulics computer codes used for coupled full-core calculations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111479Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2021.111479;
- PII
- S0029549321004313;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 384
- Journal Page Range
- vp.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54083791
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BORIC ACID; BORON; COMPUTER CODES; ENERGY ABSORPTION; ENERGY LOSSES; FUEL ASSEMBLIES; FUEL PINS; HEATING; HOMOGENEOUS MIXTURES; HYDRAULICS; LEAST SQUARE FIT; NEUTRONS; PHOTONS; PWR TYPE REACTORS; REACTION KINETICS; REACTOR CORES; STEADY-STATE CONDITIONS; SUBCOOLED BOILING; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- ABSORPTION; BARYONS; BOILING; BORON COMPOUNDS; BOSONS; DISPERSIONS; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; FERMIONS; FLUID FLOW; FLUID MECHANICS; FUEL ELEMENTS; HADRONS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; KINETICS; LOSSES; MASSLESS PARTICLES; MATHEMATICAL SOLUTIONS; MAXIMUM-LIKELIHOOD FIT; MECHANICS; MIXTURES; NUCLEONS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; SORPTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.