Published 1991
| Version v1
Book
Scaling capabilities of thermalhydraulic system codes
Creators
- 1. Pisa Univ. (Italy). Dipt. di Costruzioni Meccaniche e Nucleari
Description
Natural circulation experiments available from differently scaled integral test facilities simulating PWR plants, are the basis of the present work. Relap5/Mod2 code calculations are performed to reproduce the measured scenarios and to predict the evolution of the same phenomena in a real plant. Code results are compared with relevant experimental data. An attempt is made to evaluate the variation of the prediction accuracy when the dimensions of the involved facilities are varied; an estimation of the uncertainty in the prediction of the plant behaviour is reported. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- The 1st JSME/ASME joint international conference on nuclear engineering
- Imprint Pagination
- 1273 p.
- Journal Page Range
- v. 2 p. 243-248.
Conference
- Title
- 1. JSME/ASME joint international conference on nuclear engineering.
- Dates
- 4-7 Nov 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23075953
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; FLOW RATE; FORECASTING; HYDRAULICS; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SCALING LAWS; SIMULATION; THERMODYNAMICS
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Composed of two volumes.