Overview PWR-Blowdown Heat Transfer Separate-Effects Program Page: 4 of 16
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NUCLEAR FUEL PIN SIMULATION
The completion of the development of the computer code, PINSIM,10
makes possible the study of the relationships between nuclear and elec-
tric pin behavior. The code calculates (1) the thermal response of a
nuclear fuel pin to a specified LOCA environment, (2) the electric power
which must be supplied to a specified electric pin simulator to force
its surface to respond as a nuclear fuel pin, and (3) the actual thermal
response of an electric pin in a LOCE. These calculations may be used to
judge how well a specified experiment (LOCE) has simulated or will simu-
late a conceivable nuclear pin transient. The PINSIM code was used to
calculate the THTF power profile (in time) necessary to produce the
desired rod surface behavior for the INEL Independent Verification Test.
REFERENCES
1. Project Description, ORNL-PWR Blowdown Heat Transfer Separate-Effects
Program - Thermal Hydraulic Test Facility (THTF), ORNL/NUREG/TM-2
(February 1976).
2. RELAP4/MOD5, A Computer Program for Transient Thermal Hydraulic
Analysis of Nuclear Reactors and Related Systems Users' Manual,
ANCR/NUREG/1335 (September 1976).
3. W. G. Craddick, et al., PWR BZowdown Heat Transfer Separate-Effects
Program Data Evaluation Report - Heat Transfer for THTF Series 100,
ORNL/NUREG-45 (September 1978).
4. L. J. Ott and R. A. Hedrick, ORTCAL - A Code for THTP Heater Rod
Thermocouple Calibration, ORNL/NUREG-51, NUREG/CR-0342 (November 1978).
5. L. J. Ott and R. A. Hedrick, ORINC - A One-Dimensional Implicit
Approach to the Inverse Heat Conduction Problem, ORNL/NUREG-23
(November 1977).
6. R. A. Hedrick, et al., PWR Blowdown Heat Transfer Separate-Effects
Program Data Evaluation Report - System Response for Thermal Hydraulic
Test Facility Test Series 100, ORNL/NUREG-19 (November 1977).
7. C. B. Mullins, et al., PWR Blowdown Heat Transfer Separate-Effects
Program Data Evaluation Report - THTF Test Series II (to be published).
8. S. B. Cliff, RLPSFLUX, RELAP with Surface Flux Modifications, ORNL/
NUREG/CSD-5 (September 1978).
9. D. M. Lister, et al., COBRA III-1, An IBM-Compatible Version, ORNL/
NUREG/CSD-9 (to be published).
10. R. C. Hagar and R. A. Hedrick, PINSIM-MOD1: A Nuclear Fuel Pin/Elec-
tric Fuel Pin Simulator Transient Analysis Code (to be published).
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White, J.D. Overview PWR-Blowdown Heat Transfer Separate-Effects Program, article, January 1, 1978; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1208199/m1/4/: accessed April 17, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.