(VENUS facility modifications for pressure vessel fluence experiments)
A modification of the existing VENUS experimental facility has been proposed which will simulate, on a much reduced scale, the geometry and essential neutron transport features involved in the use of a partial length shield assembly that has been adopted at the H.B. Robinson-2 plant, and similar to designs also being incorporated or contemplated in other US reactors, to reduce fluences at critical weld locations which may be subject to pressurized thermal shock phenomena. At the present time there are no measurements available either in PWR's or test reactors to benchmark calculational methods of these fluences, which involve transport in three-dimensional geometry. A description is presented of the design of such a benchmark experiment that introduces VENUS-3 and which will be implemented by the end of the summer of 1987. Included in this description are the basic considerations which led to the proposed modifications of VENUS-1, the measurements contemplated, and the schedule of the entire program involving both the experiment and its analysis over the time interval April 1987--December 1988.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6769567
- Report Number(s):
- ORNL/FTR-2484; ON: DE90012328
- Country of Publication:
- United States
- Language:
- English
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210200* -- Power Reactors
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220600 -- Nuclear Reactor Technology-- Research
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99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BELGIUM
BENCHMARKS
CALCULATION METHODS
COMPUTER CODES
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ENRICHED URANIUM REACTORS
EUROPE
EXPERIMENTAL REACTORS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
JOINTS
L CODES
MODIFICATIONS
NEUTRON FLUENCE
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
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SHIELDING
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TEST FACILITIES
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THERMAL REACTORS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
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