LEPRICON analysis of pressure vessel surveillance dosimetry inserted into H. B. Robinson-2 during cycle 9
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5747896
A second example of applying the LEPRICON methodology to an existing pressurized water reactor is described. The present application is an analysis of ad hoc dosimetry inserted into the H.B. Robinson-2 reactor to monitor the effects on pressure vessel fluence produced by the introduction of a low-leakage fuel management scheme during cycle 9. The use of the simultaneous dosimetry at both a downcomer location and in the reactor cavity allowed a quantitative evaluation to be made by the LEPRICON procedure of the relative merits of each location. Unfolded results using the dosimetry indicate that the cumulative neutron fluence above 1 MeV originally calculated for the critical lower circumferential weld of the pressure vessel during cycle 9, 7.2 x 10/sup 17/ n/cm/sup 2/ +- 15.9%, should be adjusted upward by about one standard deviation to a value of 8.8 x 10/sup 17/ n/cm/sup 2/ with a reduced uncertainty of 10.9%.
- Research Organization:
- Oak Ridge National Lab., Oak Ridge, TN 37831
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5747896
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 96:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
LEPRICON analysis of pressure vessel surveillance dosimetry inserted into H. B. Robinson-2 during cycle 9
Application of the LEPRICON methodology to LWR pressure vessel surveillance dosimetry
The LEPRICON code system: Consolidation of transport analytical and unfolding procedures in LWR pressure vessel dosimetry
Technical Report
·
Fri Aug 01 00:00:00 EDT 1986
·
OSTI ID:5156736
Application of the LEPRICON methodology to LWR pressure vessel surveillance dosimetry
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6498987
The LEPRICON code system: Consolidation of transport analytical and unfolding procedures in LWR pressure vessel dosimetry
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5434202
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CODES
CONTAINERS
DATA PROCESSING
DOSIMETRY
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
JOINTS
L CODES
MATERIALS
NATIONAL ORGANIZATIONS
NEUTRON DOSIMETRY
NEUTRON FLUENCE
NUCLEAR FUELS
ORNL
POWER REACTORS
PRESSURE VESSELS
PROCESSING
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
ROBINSON-2 REACTOR
SPECTRA UNFOLDING
SURVEILLANCE
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CODES
CONTAINERS
DATA PROCESSING
DOSIMETRY
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
JOINTS
L CODES
MATERIALS
NATIONAL ORGANIZATIONS
NEUTRON DOSIMETRY
NEUTRON FLUENCE
NUCLEAR FUELS
ORNL
POWER REACTORS
PRESSURE VESSELS
PROCESSING
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
ROBINSON-2 REACTOR
SPECTRA UNFOLDING
SURVEILLANCE
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS