Alloy development for high burnup cladding (PWR)
- 1. Kraftwerk Union AG, Mulheim (Germany)
- 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
An overview on current alloy development for high burnup PWR fuel cladding is given. It is mainly based on literature data. First, the reasons for an increase of the current mean discharge burnup from 35 MWd / kg(U) to 70 MWd / kg(U) are outlined. From the material data, it is shown that a batch average burnup of 60-70 MWd / kg(U), as aimed by many fuel vendors, can not be achieved with stand (=ASTM-) Zry-4 cladding tubes without violating accepted design criteria. Specifically criteria which limit maximum oxide scale thickness and maximum hydrogen content, and to a less degree, maximum creep and growth rate, can not be achieved. The development potential of standard Zry-4 is shown. Even when taking advantage of this potential, it is shown that an 'improved' Zry-4 is reaching its limits when it achieves the target burnup. The behavior of some Zr alloys outside the ASTM range is shown, and the advantages and disadvantages of the 3 alloy groups (ZrSn+transition metals, ZrNb, ZrSnNb+transition metals) which are currently considered to have the development potential for high burnup cladding materials are depicted. Finally, conclusions are drawn. (author). 14 refs., 11 tabs., 82 figs
Availability note (English)
Available from INIS in electronic formFiles
30056076.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 88 p.
- Report number
- KAERI/AR--530/99
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 30056076
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; CLADDING; CORROSION; CREEP; GROWTH; MANUFACTURING; PRECIPITATION; PWR TYPE REACTORS; STANDARDS; TRANSITION ELEMENTS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; DEPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; REACTORS; SEPARATION PROCESSES; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS