Investigation of PWR accident transients with the Bethsy facility
Creators
- 1. CEA-CEN, Grenoble (France)
- 2. Framatome, Paris-la-Defense (France)
- 3. CEA-CEN, Fontenay-aux-Roses (France)
Description
BETHSY is a scaled down model of a 900 eMW Framatome pressurized water reactor (PWR) which has been designed to allow the study of PWR accident transients with the double purpose of Cathare code and Emergency Operating Procedure verification. The full operation of the facility was started in 1987. Since then, a fairly large variety of tests have been conducted which include steady state situations (single phase natural circulation, balanced and unbalanced loops, two-phase natural circulation, degraded steam generator mass inventory) as well as accident transients such as 2 inch and 6 inch cold leg breaks, steam break at pressurizer, single and multiple steam generator tube ruptures (SGTR), total loss of feedwater. In order to illustrate the ongoing Bethsy program, three different kinds of tests are briefly presented, dealing with two-phase natural circulation, intermediate cold leg breaks and multiple SGTR
Additional details
Publishing Information
- Imprint Title
- Seventeenth water reactor safety information meeting: Proceedings. Volume 3, Primary systems integrity; plant performance, testing and analysis; piping and NDE [nondestructive examination]; plant aging
- Imprint Pagination
- 529 p.
- Journal Page Range
- p. 187-202.
- Report number
- NUREG/CP--0105-Vol.3
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22091330
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EMERGENCY PLANS; FEEDWATER; HEAT TRANSFER; HYDRAULICS; NATURAL CONVECTION; PIPES; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; RUPTURES; SCALE MODELS; STEADY-STATE CONDITIONS; STEAM GENERATORS; TEST FACILITIES; TRANSIENTS; TUBES; TWO-PHASE FLOW; VERIFICATION
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; FLUID FLOW; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8910222--Vol.3.