Thermal hydraulic analysis of the AHWR containment
- 1. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
Thermal hydraulic analysis of proposed Advanced Heavy Water Reactor (AHWR) containment was carried out for loss of coolant accident (LOCA) involving 200% break in Reactor Inlet Header (RIH). The AHWR primary containment is divided into high enthalpy V1 and low enthalpy V2 volumes. Due to LOCA, steam is discharged into containment and causes pressure and temperature rise in V1 and V2 volumes. Containment analysis has been carried out using CONTRAN code which is incorporated with a mathematical model for simulating passive containment coolers. Effects of Blow-out Panel (BOP) and passive containment coolers have been studied on containment pressure and temperature transient. Inter-code comparison between CONTRAN and ASTEC code has been carried out for a BOP size. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Fourth national conference on nuclear reactor technology: emerging trends in nuclear safety
- Imprint Pagination
- 208 p.
- Journal Page Range
- [8 p.]
Conference
- Title
- 4. national conference on nuclear reactor technology
- Acronym
- NRT-4
- Dates
- 4-6 Mar 2011
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 42095265
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; ENTHALPY; HWLWR TYPE REACTORS; LOSS OF COOLANT; REACTOR SAFETY; STEAM CONDENSERS
- Descriptors DEC
- ACCIDENTS; HEAVY WATER MODERATED REACTORS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMODYNAMIC PROPERTIES; VAPOR CONDENSERS; WATER COOLED REACTORS
Optional Information
- Notes
- 12 refs., 17 figs., 1 tab.