Development of 3-D Transient Reactor Analyzer using ASTRA, THALES, and ROPER codes
Creators
- 1. Korea Nuclear Fuel Co., Daejeon (Korea, Republic of)
Description
Three dimensional core transient behaviors are spotlighted due to reactivity-initiated accident (RIA). Usually the calculation model for RIA includes the 3-D kinetics solutions with dynamic thermal-hydraulic and fuel temperature feedback. These models incorporate more detailed neutronic and thermal modeling to address more realistic response of core transient. KNF has been developing the reactor core design codes for the nuclear power plants to establish the KNF design code system. KNF code system consists of Core Neutronics (ASTRA), Thermal Hydraulic design (THALES), and Fuel Rod design (ROPER) codes. These codes have the capability of steady state and transient calculation to deal with accidental transient case. This paper presents the descriptions on integration process of above 3 design codes and benchmark calculation for verification of transient capability
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027124
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; KINETICS; NUCLEAR POWER PLANTS; REACTIVITY; REACTOR CORES; THERMAL HYDRAULICS; TRANSIENTS; VERIFICATION
- Descriptors DEC
- FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 6 refs, 4 figs, 1 tab