Published 1978
| Version v1
Report
Restricted
Validation and sensitivity analysis of ORINC
Description
The Oak Ridge INverse Code (ORINC) is used to calculate temperature and heat flux at the surface of the electric heater rods used in the PWR-Blowdown Heat Transfer Separate Effects Program. Because heat flux cannot be measured and surface temperatures are not directly measured in the Thermal Hydraulics Test Facility (THTF), which provides experimental data to ORINC, efforts have been undertaken to validate the program's results to variations in key input variables. ORINC makes use of a one dimensional, lumped parameter, implicit finite difference model of the heat conduction equation
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- K/CSD/INF--78/36
Conference
- Title
- 6. water reactor safety research meeting.
- Dates
- 6 - 9 Nov 1978.
- Place
- Germantown, MD, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10461305
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; COMPUTER CODES; FINITE DIFFERENCE METHOD; FUEL RODS; HEAT TRANSFER; LOSS OF COOLANT; MOCKUP; O CODES; ONE-DIMENSIONAL CALCULATIONS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; FUEL ELEMENTS; ITERATIVE METHODS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-781146--6.