Published 2004
| Version v1
Miscellaneous
A study on the two-phase natural circulation flow under ERVC
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
To observe and evaluate the two-phase natural circulation phenomena through the gap between the reactor vessel and the insulation in the APR1400 under the external vessel cooling, the T-HERMES (Thermo-Hydraulic Evaluations of Reactor vessel cooling Mechanisms by External Self-induced flow) program has been performed in KAERI. The HERMES-HALF study, which is one of the T-HERMES programs, is a non-heating experimental study on the two-phase natural circulation through the annular gap between the reactor vessel and the insulation. In this paper, the HERMES-HALF experimental results were presented and compared with ones of the numerical analyses using a RELAP5/ MOD3 code
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- 1466 p.
- Journal Page Range
- p. 379-380
Conference
- Title
- 2004 autumn meeting of the KNS
- Dates
- 28-29 Oct 2004
- Place
- Yongpyong (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36102342
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FLOW RATE; NATURAL CONVECTION; NUMERICAL ANALYSIS; PWR TYPE REACTORS; R CODES; REACTOR VESSELS; TWO-PHASE FLOW
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; MATHEMATICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 2 figs