Performance of containment of Indian PHWR
Creators
- 1. PSA Group, Safety Directorate, Nuclear Power Corporation of India Ltd., Nabhikiya Urja Bhavan, Anushaktinagar, Mumbai (India)
Description
This paper summarizes the various requirements and activities relevant to the testing of containment system of Indian Pressurized Heavy Water Reactor (PHWR). All Indian PHWR containments are constructed from concrete either reinforced or prestressed or a combination of both and lined with polymeric coating based on Epoxy or Vinyl in order to achieve the leak tightness necessary from the radiological considerations following an accident. The current concept includes a complete double containment (except the base raft) extended to all penetrations and some of the pipings (those open to the containment atmosphere). The primary containment fitted with a passive pressure suppression system is enveloped in the secondary containment (confinement) where slight vacuum is maintained during normal operation as well as post accident condition. The Integrated leakage Rate Test (ILRT) conducted so far on the containment indicate that the overall leakages from the containment are lower than those necessary to meet the radiological limits following a postulated accident and interception of leakages by secondary containment as per design. The details of the, tests, repairs carried out and observations are given in this paper. The experience of ILRT also indicate improvement in leak tightness in many areas. (author)
Additional details
Publishing Information
- Publisher
- Prime Time Education
- Imprint Place
- Mumbai (India)
- ISBN
- 81-8372-028-5
- Imprint Title
- Proceedings of national conference on operating experience of nuclear reactors and power plants: book of preprints
- Imprint Pagination
- 1313 p.
- Journal Page Range
- p. 268-274
Conference
- Title
- operating experience of nuclear reactors and power plants; NRT-3: 3. nuclear reactor technology
- Acronym
- OPENUPP-2006
- Dates
- 13-15 Nov 2006
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 38040200
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; LEAK TESTING; LOSS OF COOLANT; PHWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING
Optional Information
- Notes
- 8 refs., 1 fig.