Calculation of the neutron source distribution in the venus PWR engineering mock-up and comparison with experimental measurements
Conference
·
OSTI ID:6758880
The VENUS experiment is sponsored by the USNRC in conjunction with CEN/SCK in Mol, Belgium. The VENUS configuration consists of a central water hole, surrounded by a 2.888 cm thick inner sheet baffle. The inner core zone in the immediate vicinity of the inner baffle contains 752 3.3% /sup 235/U, zircalloy fuel cells, with 48 pyrex rods interspersed among them. The outer core zone contains 1800 4.0% /sup 235/U, steel clad fuel cells. The core itself is surrounded by a 2.858 cm thick outer steel baffle, a water reflector, a 4.972 cm thick steel core barrel, a water gap, a neutron pad, and the pressure vessel. The primary aim of this study is to calculate the VENUS neutron source distribution, as part of the USNRC's overall program goal of benchmarking RPV fluence calculations. Of particular concern is the accuracy of the source calculation near the core-baffle interface, which is the important region for contributing to RPV fluence. The accuracy of the calculations is evaluated by comparison with gamma scan measurements performed by CEN/SCK.
- Research Organization:
- Oak Ridge National Lab., TN (USA); Louisiana State Univ., Baton Rouge (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6758880
- Report Number(s):
- CONF-840614-69; ON: DE84014259
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-core and ex-core calculations of the VENUS simulated PWR benchmark experiment
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Conference
·
Thu Oct 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5860008
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Conference
·
Tue Dec 31 23:00:00 EST 1985
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·
OSTI ID:6995132
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Technical Report
·
Wed Aug 01 00:00:00 EDT 1984
·
OSTI ID:6505493
Related Subjects
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CONTAINERS
DISTRIBUTION
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210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
DISTRIBUTION
EMBRITTLEMENT
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
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SAFETY
SPATIAL DISTRIBUTION
TEST FACILITIES
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS