Published 1981
| Version v1
Report
Restricted
High-temperature neutron shield
Description
This report describes the use of boron carbide (B4C) and Titanium hydride (TiH16) as neutron shielding material for a 50-megawatt (thermal) experimental nuclear reactor. The Loss-of-Fluid Test (LOFT) pressurized water reactor is used to perform loss-of-coolant experiments (LOCEs) on an operating reactor. The plant is scaled to simulate the response of a large pressurized water reactor during a loss-of-coolant accident
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82005639.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- EGG-M--06781
Conference
- Title
- ANS winter meeting.
- Dates
- 29 Nov - 4 Dec 1981.
- Place
- San Francisco, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13696707
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON CARBIDES; LOFT REACTOR; RADIATION STREAMING; SHIELDING; SPECIFICATIONS; TITANIUM HYDRIDES
- Descriptors DEC
- BORON COMPOUNDS; CARBIDES; CARBON COMPOUNDS; HYDRIDES; HYDROGEN COMPOUNDS; PWR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-811103--79.