Calorimetric and transport properties of Zircalloy 2, Zircalloy 4, and Inconel 625

Journal Article · Fri Jul 01 00:00:00 EDT 1994 · International Journal of Thermophysics

DOI:https://doi.org/10.1007/BF01563797· OSTI ID:75396

Maglic, K D; Perovic, N Lj; Stanimirovic, A M ^[1]

---

1. Institute of Nuclear Sciences, Belgrade (Yugoslavia)

This paper presents the measurements and the results on thermal and electrical transport properties of three nuclear reactor cladding materials: Zircalloy 2, Zircalloy 4, and Inconel 625. Study of these materials constituted a part of the IAEA coordinated research program aimed at the generation and establishment of a reliable and complete database of the thermal properties of reactor materials. Measured properties include thermal diffusivity, specific heat, and electrical resistivity. Thermal diffusivity was measured by the laser pulse technique. Specific heat and electrical resistivity were measured using a millisecond-resolution direct electrical pulse heating technique. Thermal conductivity was computed from the experimentally determined thermal diffusivity and specific heat functions and the room temperature density values. Measurements were performed in the 20 to 1500{degrees}C temperature range, depending on the material and property concerned.

• Sponsoring Organization: USDOE
• OSTI ID: 75396
• Journal Information: International Journal of Thermophysics, Vol. 15, Issue 4; Other Information: PBD: Jul 1994
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
36 MATERIALS SCIENCE
INCONEL 625
THERMAL DIFFUSIVITY
SPECIFIC HEAT
THERMAL CONDUCTIVITY
ELECTRIC CONDUCTIVITY
ZIRCALOY 2
ZIRCALOY 4