Published 1986 | Version v1
Report Restricted

Alternate method of decay-heat removal in a C-E plant following a SBLOCA

Creators

Description

The use of an atmospheric steam-dump procedure to cool and depressurize a Combustion-Engineering plant, Calvert Cliffs-1, following small-break loss-of-coolant accidents with failure of the high-pressure injection system to operate has been investigated. The procedure was effective in depressuizing the primary to the low-pressure injection system operating pressure and design temperature using water supplies from the safety-grade condensate water storage tank only. The procedure was found to be effective even if additional failures occurred. Specifically, low-pressure injection conditions were attained if only a single atmospheric dump valve was available or if the safety-injection tanks (accumulators) were not available

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86004720.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
LA-UR--85-4146

Conference

Title
Thermal reactor safety meeting.
Dates
2-6 Feb 1986.
Place
San Diego, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17062787
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; CALVERT CLIFFS-1 REACTOR; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; REACTOR SHUTDOWN; RISK ASSESSMENT
Descriptors DEC
ACCIDENTS; CONVECTION; COOLING SYSTEMS; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-860204--21.