Published 2014
| Version v1
Miscellaneous
Validation of SOCRAT-BN code on rod bundle experiments
- 1. Nuclear Safety Institute, Moscow (Russian Federation)
Description
SOCRAT-BN code is developed for the analysis of design and beyond design basis accidents at NPPs with liquid sodium as a coolant. To simulate the behavior of the coolant in the reactor core heat transfer and friction in rod bundle geometry are required to consider. The code SOCRAT-BN uses specialized closing relations to simulate rod bundles. The article describes the validation of the code SOCRAT-BN on experiments with fuel rod imitators in the triangular geometry with a wire-wound. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
- Imprint Pagination
- 2846 p.
- Journal Page Range
- 14 p.
Conference
- Title
- 10. international topical meeting on nuclear thermal hydraulics, operation and safety
- Acronym
- NUTHOS-10
- Dates
- 14-18 Dec 2014
- Place
- Ginowan, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47051585
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANTS; DESIGN BASIS ACCIDENTS; FRICTION; FUEL ELEMENT CLUSTERS; FUEL PINS; HEAT TRANSFER; LOSS OF FLOW; S CODES; SODIUM; THERMAL HYDRAULICS; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDRAULICS; MECHANICS; METALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; TESTING
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1355.pdf; 2 refs., 14 figs., 7 tabs.