Fuel element development for the ACPR Upgrade
- Sandia Laboratories, Albuquerque, NM (United States)
Two high heat capacity fuels are under consideration for the upgrade of the Annular Core Pulse Reactor. These fuels are BeO-UO{sub 2} and (UC-ZrC)- graphite. An extensive in-pile testing program is being conducted to develop both fuels for use in the central portion of a two region core. A major part of the testing program is directed at maximizing the failure resistance of the candidate fuels when subjected to rapid pulse heating. The high heat capacity fuel element will replace a part of the present U-ZrH{sub 1.62} fuel and is limited to the same outer dimensions as the current fuel element. The in-pile testing program utilizes fuel pellets with a diameter of 3.3 cm. The specimens are pulse heated in the ACPR to the temperature range required for use in the upgraded reactor and the post test condition is examined to determine the degree of cracking. Since large thermal stresses are induced by these tests, various fuel fabrication techniques and geometry changes have been examined. The results of these tests have shown that a dual-slotted annulus configuration can be used with both BeO-UO{sub 2} and (UC-ZrC)- graphite to reduce thermal stresses and improve the survival of an individual specimen. Both single and multiple pulse tests are being performed. The fuels testing results is being used to develop the fuel element design which is complicated by high operating temperatures which are up to 1500 deg. C for the BeO-UO{sub 2} and 2000 deg. C or above for the (UC-ZrC)-graphite. The fuel element design requires an insulating liner between the fuel and clad to prevent excessive clad temperatures. The liner materials are molybdenum for the BeO-UO{sub 2} fuel element and graphite for the (UC-ZrC)-graphite fuel element. In-pile testing of prototype fuel elements is anticipated. (author)
- Research Organization:
- General Atomic Co., San Diego, CA (United States); Univ. of California, Berkeley, CA (United States)
- OSTI ID:
- 21152778
- Report Number(s):
- INIS-US-09N0184; TOC-7; TRN: US09N0189030833
- Resource Relation:
- Conference: 4. TRIGA owners' conference, Salt Lake City, UT (United States), 1-3 Mar 1976; Other Information: Country of input: International Atomic Energy Agency (IAEA); Abstract only; Related Information: In: 4. TRIGA owners' conference. Papers and abstracts, 356 pages.
- Country of Publication:
- United States
- Language:
- English
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