Experimental and PULSAR-2 calculational data comparison for different fuel assembly and reactors
- 1. RNTs Kurchatovskij Inst., Moscow (Russian Federation)
Description
Examples of verification of the computer code PULSAR-2 intended for simulating the behaviour of fuel element thermal-physical, strength and stress-strain characteristics in power reactors operating under quasi-stationary, transient and variable conditions are discussed. The computer code is the first mechanic-thermal-physical code officially certified as applicable for simulation of the fuel element behaviour in power reactors. The comparison of simulation results with experimental data for the fuel elements which operated for one, three, four and five core lifetimes in the WWER-440, WWER-1000 and MR reactors is made. The conclusion is made that calculated estimates of the changes in fuel element diameters and their elongations, as well as gas release and pressure inside the fuel cans after their cooling agree well with the data of post-reactor studies
Additional details
Additional titles
- Original title (Russian)
- Сравнение экспериментальных и расчетных данных по PULSA-2 для различных TVS и реакторов
Publishing Information
- Journal Title
- Atomnaya Ehnergiya
- Journal Volume
- 83
- Journal Issue
- 3
- Journal Page Range
- p. 159-164
- ISSN
- 0004-7163
- CODEN
- AENGAB
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 30034247
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; ELONGATION; EVALUATED DATA; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; FUEL CANS; GASES; HOLLOW FUEL RODS; LOVIISA-2 REACTOR; MEDIUM PRESSURE; P CODES; POST-IRRADIATION EXAMINATION; POWER DENSITY; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; THEORETICAL DATA; TIME DEPENDENCE; WWER-5 REACTOR
- Descriptors DEC
- COMPUTER CODES; DATA; DEFORMATION; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; FUEL RODS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 6 refs., 6 figs., 4 tabs.