System Analysis Handbook
Description
This handbook provides simple procedures for calculating the behavior of light water reactors during a variety of incidents. It provides an additional tool for assessment of ongoing and postincident behavior. The handbook consists of a main body describing generic procedures, an appendix providing specific design data for a limited number of plants for application with the procedures, and an appendix listing existing and planned BWR and PWR plants by containment types and thermal-hydraulic parameters. The procedures are currently limited to break flow rate, decay heat power and integrated power, steam generation from decay heat, mass balance, shutdown margin, natural circulation, noncondensable gas generation, dose estimates, DNB evaluation, void formation in the upper head, and torus heatup
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A07/MF A01 as TI85006086.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 127 p.
- Report number
- NUREG/CR--4041
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064720
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; BWR TYPE REACTORS; DEPARTURE NUCLEATE BOILING; FLOW RATE; HEAT TRANSFER; HYDRAULICS; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BOILING; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2354.