High temperature properties of J-AlloyTM
- 1. Nuclear Fuel Industries, Ltd., Kumatori, Osaka (Japan)
- 2. Mitsubishi Nuclear Fuel Co., Ltd., Tokai, Ibaraki (Japan)
- 3. Kansai Electric Power Co., Inc., Osaka (Japan)
Description
The J-AlloyTM, Zr-Nb based alloy aiming for expansion of safety margins under high duty operation, is under development as an advanced PWR fuel cladding tube with superior corrosion resistance. In this study, non-irradiated J2 (Zr-1.6Nb-0.1Cr), one of the J-AlloyTM candidates, was subjected to a series of high temperature tests. In order to obtain high temperature properties of J2, specific heat measurement, high temperature creep test and high temperature burst test were conducted, and it was observed that the high temperature properties of J2 were equivalent to Zircaloy-4 in the α phase and β phase. But difference between J2 and Zircaloy-4 was observed in the temperature range of α+β phase. This difference is due to the alteration of phase transformation temperature caused by Nb addition. Since the difference is slight, it was confirmed that J2 has sufficient properties as an advanced PWR fuel cladding tube. In order to confirm the applicability of J2 cladding tube to LOCA condition, an integral thermal shock test was conducted with parameters of holding temperature, ECR and hydrogen concentration of cladding tube. The test result demonstrated that the fracture limit of J2 meets the 15%-ECR LOCA criterion in Japan. Therefore, the applicability of J-AlloyTM cladding tube to LOCA condition was confirmed. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)
- Imprint Pagination
- 784 p.
- Journal Page Range
- 4 p.
Conference
- Title
- 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting
- Acronym
- WRFPM 2014
- Dates
- 14-17 Sep 2014
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47079916
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CALORIMETRY; CLADDING; CORROSION RESISTANCE; CORROSION RESISTANT ALLOYS; CREEP; ECCS; FUEL-CLADDING INTERACTIONS; LOSS OF COOLANT; NIOBIUM ALLOYS; PWR TYPE REACTORS; QUENCHING; REACTOR ACCIDENT SIMULATION; STRAINS; THERMAL SHOCK; ZIRCALOY 4; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100076.pdf; 9 res., 6 figs., 2 tabs.