Containment studies facility: experiments and analytical studies
Creators
- 1. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
Containment Studies Facility (CSF) is a test facility has been set up at BARC for carrying out experiments related to nuclear reactor containment. It consists of a containment model and a pressure vessel (or PHTM vessel). Containment thermal hydraulic experiments were carried out in CSF for 50 bar and 75 bar blowdown conditions for simulating containment pressure and temperature transients following pipe break simulating LOCA/MSLB. Pressure, temperature and other transient parameters were recorded during the experiments. The experimental results were compared with outputs of modeling carried out using various codes like RELAP, ASTEC and CONTRAN etc. The details of the experimental and analytical studies conducted are presented in this paper. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the international workshop on new horizons in nuclear reactor thermal hydraulics and safety
- Imprint Pagination
- 91 p.
- Journal Page Range
- [2 p.]
Conference
- Title
- international workshop on new horizons in nuclear reactor thermal hydraulics and safety
- Acronym
- IW-NRTHS 2014
- Dates
- 13-15 Jan 2014
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 45080296
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; C CODES; CONTAINMENT; LOSS OF COOLANT; PHWR TYPE REACTORS; R CODES; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FLUID MECHANICS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; REACTOR ACCIDENTS; REACTORS
Optional Information
- Notes
- 7 refs., 4 figs.