Contact conductance between cladding/pressure tube and pressure tube/calandria tube of advanced thermal reactor (ATR)
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
In some postulated accidents with coincident loss of emergency coolant injection of the Advanced Thermal Reactor (ATR), the rate of heat transfer to the heavy water moderator that acts as heat sink for the decay heat depends on the contact conductance between cladding and pressure tube, and the same between pressure and calandria tubes. Experiments were performed to assess these contact conductances for clean plates and plates with simulated crud of Fe2O3 powder that is the main ingredient of the crud, and the applicable correlations were also studied. Test specimens were cut from actual pressure tube made of Zr-2.5%Nb and calandria tube made of Zircaloy-2 and flattened to sizes. The artificial waviness of various kinds of height and wave length of 10 mm was machined on the surface of the pressure tube specimen. The ranges of contact pressure, roughness, specimen temperature and gas pressure were from 0.5 to 7 MPa, 4.8 to 100 μm, 400 to 840 K and 0.001 Torr to atmospheric respectively. The experimental results without crud compare favorably with Tachibana's correlation. The experimental contact conductances with crud are found to be lowered. Since Tachibana's correlation was not applicable to the present situation, the empirical correlation was proposed. The correlation fitted well with the experimental values. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 31
- Journal Issue
- 7
- Journal Page Range
- p. 726-734.
- ISSN
- 0022-3131
- CODEN
- JNSTAX
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 25074256
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; BENCH-SCALE EXPERIMENTS; CALANDRIAS; CORRELATIONS; EMULSIONS; FUEL CANS; JATR REACTOR; PRESSURE TUBES; ROUGHNESS; TEMPERATURE DEPENDENCE; THERMAL CONDUCTION; ZIRCALOY 2
- Descriptors DEC
- ALLOY-ZR98SN-2; ALLOYS; CHROMIUM ADDITIONS; COLLOIDS; CONTAINERS; CORROSION RESISTANT ALLOYS; DISPERSIONS; ENERGY TRANSFER; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; IRON ADDITIONS; MATERIALS; NATURAL URANIUM REACTORS; NICKEL ADDITIONS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SURFACE PROPERTIES; THERMAL REACTORS; TIN ALLOYS; TUBES; WATER COOLED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS