Simulation of critical experimental nuclear arrays with the Serpent code
Creators
- 1. IPN, Escuela Superior de Fisica y Matematicas, 07738 Ciudad de Mexico (Mexico)
Description
From the Nea/Nsc/Doc/(95) manual that contains criticality safety benchmark specifications, which have been derived from experiments conducted at several critical nuclear facilities worldwide, four experimental arrangements were chosen for simulation with the Monte Carlo Serpent code. The following experimental arrangements were simulated: 18 configurations of low enrichment UO2 fuel rod arrangements with water to fuel volume ratios of 1.5 to 3.0, with specification number Leu-Comp-Therm-006; 29 configurations of U(2.35)O2 fuel bar arrangements moderated with water and reflected by two walls of lead, depleted uranium or steel, with specification number Leu-Comp-Therm-017; bare metallic Pu-239 sphere (4.5 at. %, 240-Pu, 1.02 wt. % Ga), with specification number Pu-Met-Fast-001 and the critical reference experiment of a plutonium sphere reflected by thorium, with specification number Pu-Met-Fast-008. This paper describes the critical experimental arrangements; the geometry with its dimensions, the composition of the materials constituting the fuel, the moderator, the support structures and the material used as a reflector is provided. Likewise, the results of the multiplication factor obtained with the Serpent code and the comparison of these results with the experimental result are presented. It was shown that the simulation models prepared to simulate these experimental arrangements with the Serpent code were correctly designed, since the differences were minimal between the numerical results of the multiplication factor versus the experimental ones. Additionally, the validity and reliability of this code was confirmed for use in neutron calculations for any nuclear fuel arrangement. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares. Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), E-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Additional titles
- Original title (Spanish)
- Simulacion de arreglos nucleares experimentales criticos con el codigo Serpent
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 15 p.
Conference
- Title
- peaceful applications of nuclear energy for the Mexico benefit
- Original Conference Title
- 30. Congreso Anual de la SNM: aplicaciones pacificas de la energia nuclear en beneficio de Mexico
- Acronym
- 30. SNM Annual Congress
- Dates
- 4-7 Aug 2019
- Place
- Monterrey, Nuevo Leon (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 51005301
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONFIGURATION; DEPLETED URANIUM; FUEL RODS; GEOMETRY; LEAD; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEA; NEUTRONS; NUCLEAR FUELS; PLUTONIUM; PLUTONIUM 239; PLUTONIUM 240; SPECIFICATIONS; SPHERES; STEELS; THORIUM; URANIUM DIOXIDE; WATER
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALLOYS; ALPHA DECAY RADIOISOTOPES; BARYONS; CALCULATION METHODS; CARBON ADDITIONS; CHALCOGENIDES; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FERMIONS; FUEL ELEMENTS; FUELS; HADRONS; HEAVY NUCLEI; HYDROGEN COMPOUNDS; INTERNATIONAL ORGANIZATIONS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MATERIALS; MATHEMATICS; METALS; NUCLEI; NUCLEONS; OECD; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; TRANSITION ELEMENT ALLOYS; TRANSURANIUM ELEMENTS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES