Progress in shielding design in the Dragon Project. Project DRAGON

Technical Report · Mon Apr 15 04:00:00 EST 1963

OSTI ID:4136327

Crawley, D. B.

The Dragon Reactor Experiment is a 20 MW High Temperature gas pooled reactor being built as a joint OECD project at the United Kingdom Atomic Energy Establishment at Winfrith, Dorset. The primary objective of the Dragon reactor is to provide design and operating experience of a reactor of this type before building a full scale power generating plant. Major objectives include obtaining general physios information, testing fuel elements of advanced design, and controlling the release of fission products in an active primary coolant circuit. The calculations for the Dragon reactor shield design were initiated in 1957, based largely on simple semi-empirical methods of comparison with existing reactor shields at Harwell. Later computations are based on the method of calculation developed by the Shielding group of Reactor Division, Harwell. This paper sets out to summarise the work that has been carried out to solve the shield design problems encountered, and also the preliminary investigations into the shielding requirements for a 1250 MW High Temperature power reactor design study.

• Research Organization: Atomic Energy Establishment (AEE), Winfrith, England (United Kingdom)
• Sponsoring Organization: Atomic Energy Establishment (AEE)
• NSA Number: NSA-24-040944
• OSTI ID: 4136327
• Report Number(s): DP-Report--175; CONF-630511--10
• Country of Publication: United Kingdom
• Language: English

Related Subjects

DESIGN
DRAGON
HIGH-TEMPERATURE GAS-COOLED REACTOR EXPERIMENT/ shielding for
design calculations for
N38130* --Power Reactor Development--Shielding
REACTORS
SHIELDING