TUCOP failure threshold test CO6R [electronic resource].
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1984.
- Physical Description:
- Pages: 32 : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The C06R test was the sixth single-pin test in the collaborative US/UK PFR/TREAT transient testing program. It was designed to study the mechanism, time and location of cladding failure and first fuel escape in an intermediate channel transient undercooling - overpower accident (TUCOP). It complements the LO5/sup 2/ and LO7/sup 3/ tests which studied post failure fuel dispersal in a similar hypothetical accident. The test fuel was a single irradiated driver fuel pin taken from the UK's Prototype Fast Reactor (PFR) after approx.4% peak burnup. The C06R test has produced evidence that both pre and post failure internal fuel motions produce net fuel worth decreases that would help mitigate a TUCOP accident in an LMFBR. Furthermore, the high axial failure location will prevent worth increases even if emergent fuel momentarily accumulates at the failure site before it disperses upward.
- Report Numbers:
- E 1.99:hedl-sa-3182
E 1.99: conf-841105-71
- Other Subject(s):
- Lmfbr Type Reactors
- Fuel Element Failure
- Transient Overpower Accidents
- Reactor Safety Experiments
- Thermal Stresses
- Fuel Cans
- Fuel Pins
- Research Programs
- Breeder Reactors
- Epithermal Reactors
- Fast Reactors
- Fbr Type Reactors
- Fuel Elements
- Liquid Metal Cooled Reactors
- Reactor Accidents
- Reactor Components
- Published through SciTech Connect.
Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Washington, DC, USA, 11 Nov 1984.
Herbert, R.; Culley, G.E., Ferrell, P.C.; Woods, W.J.
Hanford Engineering Development Lab., Richland, WA (USA)
- Funding Information:
View MARC record | catkey: 14368029