PRESCON2 predictions of Point Lepreau containment events
Creators
- 1. Sadiq Yousuf Group Inc., Cambridge, Ontario (Canada)
- 2. New Brunswick Power, Lepreau, New Brunswick (Canada)
- 3. Atlantic Nuclear Services Ltd., Fredericton, New Brunswick (Canada)
Description
PRESCON2 code was originally developed to predict containment peak pressure for large LOCA accidents. Further enhancements were added to increase its capability to predict long term containment thermal hydraulic behaviour. Recently, additional models for containment subsystems are incorporated in PRESCON2 that enabled the code to simulate low pressurization transients. These models with improved solution methodology extended the code performance for the range of events with extremely small discharges into containment. Further improvement in the methodology for using PRESCON2 resulted in the capability to simulate steady state initial condition for different states of ventilation system resulting in different initial reactor building conditions. To prove and validate the use of new methodology of code use and the new models, PRESCON2 is used to predict three events which occurred at the Point Lepreau generating station. The following paper provides a comparison of pressures predicted by PRESCON2 against measurement made at the station. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-47-X
- Imprint Title
- Simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [16 p.]
Conference
- Title
- 5. International conference on simulation methods in nuclear engineering
- Dates
- 8-11 Sep 1996
- Place
- Montreal, PQ (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 33018539
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT; HYDRAULIC CONDUCTIVITY; LOSS OF COOLANT; P CODES; POINT LEPREAU-1 REACTOR; RADIONUCLIDE KINETICS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; KINETICS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 1 ref., 1 tab., 9 figs.