Published 1986
| Version v1
Book
Comparison of PODMIX calculations with operational data from the instrumented boiler pods at Hartlepool and Heysham I
- 1. Central Electricity Research Labs., Leatherhead (UK)
- 2. Central Electricity Generating Board, Manchester (UK). North Western Region
Description
The measured distributions of steam and metal temperatures in the helical coil, once-through boilers at Hartlepool and Heysham I have been investigated using the two-dimensional, steady-state program PODMIX. A sensitivity analysis of the input parameters to PODMIX showed that appreciable modifications to the design data on boiler geometry and gas flow distribution were required in order to obtain good agreement between the program predictions and plant operational data in the 40% to 100% load range. With the revised input data the program was used to specify a set of boiler feed ferrules which should enable the Heysham I boilers to operate at full load within the specified temperature constraints. (author)
Additional details
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (UK)
- ISBN
- 0 7277 0269 6
- Imprint Title
- Boiler dynamics and control in nuclear power stations 3
- Imprint Pagination
- 342 p.
- Journal Page Range
- p. 237-246.
Conference
- Title
- 3. international conference on boiler dynamics and control in nuclear power stations.
- Dates
- 21-25 Oct 1985.
- Place
- Harrogate (UK).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18032753
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILERS; COMPARATIVE EVALUATIONS; FLOW RATE; GAS FLOW; GEOMETRY; HARTLEPOOL REACTOR; HELICAL CONFIGURATION; HEYSHAM-A REACTOR; P CODES; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; TEMPERATURE DISTRIBUTION; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- AGR TYPE REACTORS; CARBON DIOXIDE COOLED REACTORS; COMPUTER CODES; CONFIGURATION; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATHEMATICS; POWER REACTORS; REACTORS; THERMAL REACTORS