Development and verification of open reactor simulator ADPRES
Creators
- 1. Abu Dhabi Polytechnic, Mohammed Bin Zayed City, Abu Dhabi (United Arab Emirates)
Description
Highlights: • Abu Dhabi Polytechnic Reactor Simulator (ADPRES) is an open source reactor simulator which can be used and modified by everyone. • ADPRES solves static and time-dependent three-dimensional, multi-group neutron diffusion equation in Cartesian geometries. • ADPRES' input is straight forward and it has many features of today's modern reactor simulators. • ADPRES has been verified for both static and time-dependent reactor benchmarks. • ADPRES can be obtained from author's GitHub repository. - Abstract: Abu Dhabi Polytechnic Reactor Simulator (ADPRES) is an open source reactor simulator recently developed at Abu Dhabi Polytechnic. It solves static and time-dependent three-dimensional, multi-group neutron diffusion equation in Cartesian geometries. Fourth order standard Nodal Expansion Method (NEM) is implemented in ADPRES for spatial discretization. The time-dependent diffusion equation is numerically solved by fully-implicit scheme. ADPRES input is straight-forward and designed with minimal keywords. ADPRES also has most features of today's modern reactor simulators. In this paper, ADPRES solutions for several reactor benchmarks were verified. The first part of PWR MOX/UO2 core benchmark was used to verify ADPRES on static reactor problem. For transient reactor problems, LMW three-dimensional and NEACRP 3D PWR transient benchmarks were used. ADPRES solutions were generally accurate and consistent with the solutions from other computer codes. The source codes can be found in the author's GitHub repository.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.06.049Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.06.049;
- PII
- S0306454919303676;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 133
- Journal Page Range
- p. 580-588
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008008
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; NEUTRON DIFFUSION EQUATION; NODAL EXPANSION METHOD; PWR TYPE REACTORS; REACTOR KINETICS; REACTOR SIMULATORS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; UNITED ARAB EMIRATES; URANIUM DIOXIDE; VERIFICATION
- Descriptors DEC
- ACTINIDE COMPOUNDS; ANALOG SYSTEMS; ARAB COUNTRIES; ASIA; CALCULATION METHODS; CHALCOGENIDES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; FUNCTIONAL MODELS; KINETICS; OXIDES; OXYGEN COMPOUNDS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTORS; SIMULATORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.