Published 2018 | Version v1
Miscellaneous

Estimate of the thermal conductance between pressure tube and calandria tube upon contact

Creators

  • 1. Point Lepreau Nuclear Generating Station, NB (Canada)

Description

To confirm the integrity of the fuel channel after the contact with a given moderator subcooling in case of a large LOCA event, an analytical methodology has been developed to simulate the process of the pressure tube heatup, ballooning, contacting its surrounding calandria tube and the heat transfer to the moderator. Within this methodology, the pressure tube/calandria tube contact thermal conductance is a key parameter to the heat transfer process. In this work, the thermal contact conductance at 1MPa and 2MPa of the pressure tube pressure in case of film boiling heat transfer on the calandria tubes was estimated based on existing experiments. The estimated values were then applied in transient simulations for other tests to confirm its reasonableness. (author)

Part of:
The nuclear future : challenges and innovation. 38th Annual CNS conference and 42nd CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-27-8
Imprint Title
The nuclear future : challenges and innovation. 38th Annual CNS conference and 42nd CNS/CNA student conference
Imprint Pagination
169 Megabytes
Journal Page Range
[8 p.]

Conference

Title
38. Annual CNS conference and 42. CNS/CNA student conference
Dates
3-6 Jun 2018
Place
Saskatoon, Saskatchewan (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
50012894
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; FUEL CHANNELS; HEAT TRANSFER; LOSS OF COOLANT; MODERATORS; PRESSURE TUBES; SIMULATION
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES

Optional Information

Notes
7 refs., 9 figs.