Published November 1978
| Version v1
Report
Restricted
The design of electrical heater pins to simulate transient dryout and post-dryout of water reactor fuel
Description
A theoretical assessment of indirect and direct filled heater simulations of nuclear reactor fuel pins is described. For reasons of fast temperature response, a direct unfilled heater, with thermocouples buried in the walls, is recommended for studies of Loss-of-Coolant Accidents leading to dryout, post-dryout and rewetting. A design of heater pins, for use in SGHWR or PWR experiments, and compatible with existing 9MW power supplies, is described. Experiments to confirm collapse pressure calculations at 10000C and thermocouple response times are also reported. (author)
Availability note (English)
MF available from INIS under the Report Number; Also available from H.M. Stationery Office, price Pound1.50.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- ISBN
- 085182 044 1
- Imprint Pagination
- 34 p.
- Report number
- AEEW-M--1558
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 10482755
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CRITICAL HEAT FLUX; DRYOUT; EXPERIMENTAL DATA; FUEL PINS; GRAPHS; HEAT TRANSFER; HEATERS; LOSS OF COOLANT; PWR TYPE REACTORS; REWETTING; SGHWR REACTOR; SIMULATION; TEMPERATURE MEASUREMENT; THERMOCOUPLES
- Descriptors DEC
- ACCIDENTS; DATA; DATA FORMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; HEAVY WATER MODERATED REACTORS; INFORMATION; MEASURING INSTRUMENTS; NUMERICAL DATA; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS