Published 1983 | Version v1
Report Open

Independent assessment of the natural-circulation capability of the heterogeneous-core CRBR

Creators

Description

This summary describes results of an independent assessment of the natural circulation capability of the heterogeneous core Clinch River Breeder Reactor Plant (CRBRP) following station blackout. The primary tool for this analysis is the Super System Code (SSC) which was developed at Brookhaven National Laboratory. Comparisons are made between SSC and the project's analysis, with emphasis on the effect of inter-assembly flow redistribution

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as DE83014437.

Files

15001913.pdf

Files (79.1 kB)

Name Size Download all
md5:d11eb0042c9c5f463c07839756a82aef
79.1 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
BNL-NUREG--33199

Conference

Title
American Nuclear Society winter meeting.
Dates
30 Oct - 4 Nov 1983.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15001913
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT; AFTER-HEAT REMOVAL; CLINCH RIVER BREEDER REACTOR; COMPUTER CALCULATIONS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; NATURAL CONVECTION; REACTOR SAFETY; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; CONVECTION; DISTRIBUTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SODIUM COOLED REACTORS

Optional Information

Secondary number(s)
CONF-831047--9.