Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant
Description
An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A99/MF A01 - GPO as TI86004581.Files
17078731.pdf
Files
(23.3 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:422d9caeb3d30510e2cddd6888faab1b
|
23.3 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 668 p.
- Report number
- NUREG/CR--4022
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17078731
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALVERT CLIFFS-1 REACTOR; EVALUATION; FAILURES; FRACTURE MECHANICS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR VESSELS; RISK ASSESSMENT; THERMAL SHOCK; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MECHANICS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/TM--9408.