Document Details
PURL
Title:
STEAM GENERATION IN A REACTOR
Author(s):
Subject Terms:
100 AreasHANFORD PRODUCTION REACTORSN ReactorReactor TechnologyREACTORS-HEAT TRANSFERSTEAM ENGINEERING-POWER RECOVERY
Document Location:
DOE Public Reading Room - Hanford Battelle P.O. Box 999 MS H2-53 Richland WA 99352 (509)372-7443
Document Type:
REPORT
Publication Date:
1955 Jul 21
Declassification Date:
1955 Aug 12
Declassification Status:
Declassified
Document Pages:
21
Accession Number:
RL-1-362375
Document Number(s):
HW-38242
Originating Research Org.:
GE - HAPO
OpenNet Entry Date:
2004 Feb 23
OpenNet Modified Date:
2015 Aug 14
Description/Abstract:
TEST WITH FORCED CIRCULATION BOILING HEAT TRANSFER TO STEAM - H20 MIXTURES WERE PERFORMED WITH A 0.1-INCH THICK ANNULUS, 1.43 INCHES ID, AND 23.5 FT LONG. SURFACES WITH HEAT FLUXES FROM 10 TO THE FIFTH POWER TO 7X10 TO THE FIFTH POWER BTU/HR-FT TO THE SECOND POWER WERE COOLED PRODUCING EXIT STEAM QUALITIES UP TO 60% BY WT AT PRESSURES FROM 100 TO 800 PSI. THE GENERAL TRENDS OF THE DATA ARE PRESENTED TO INDICATE THE ALLOWABLE STEAM GENERATION IN A REACTOR AND RELATED PROBLEMS ARE DISCUSSED.