Pre-Test Calculation of PKL III G3.1 Test
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The large-scale test facility PKL is a scaled-down model of a 4-loop pressurized water reactor (PWR) of the 1300 MWe class. The PKL test facility models the entire primary system and essential parts of the secondary system without a turbine and condenser. Though all elevations are scaled 1:1, volumes, power and mass flows are modelled by a scaling factor of 1/145. The maximum power of 2.5 MW corresponds to 10 % of the rated thermal power in commercial plants. The maximum pressure of the primary system is 45 bars. In this study, the PKL III G3.1 test was simulated by the MARS-KS code as part of a pre-test calculation where no comparative experimental data is provided except for the boundary and initial test conditions. The objective of the PKL III G3.1 test is the investigation of the fast cool-down transient by a main steam line break (MSLB)
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
- 41027305
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; EXPERIMENTAL DATA; M CODES; PWR TYPE REACTORS; STEAM LINES; TEST FACILITIES; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; PIPELINES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 3 figs, 1 tab