Analysis code for pressure in reactor containment vessel of ATR. CONPOL
Description
For the evaluation of the pressure and temperature in containment vessels in the events which are classified in the abnormal change of pressure, atmosphere and others in reactor containment vessels in accident among the safety evaluation events of the ATR, the analysis code for the pressure in reactor containment vessels CONPOL is used. In this report, the functions of the analysis code and the analysis model are shown. By using this analysis code, the rise of the pressure and temperature in a containment vessel is evaluated when loss of coolant accident occurs, and high temperature, high pressure coolant flows into it. This code possesses the functions of computing blow-down quantity and heat dissipation from reactor cooling facility, steam condensing heat transfer to containment vessel walls, and the cooling effect by containment vessel spray system. As for the analysis techniques, the models of reactor cooling system, containment vessel and steam discharge pool, and the computation models for the pressure and temperature in containment vessels, wall surface temperature, condensing heat transfer, spray condensation and blow-down are explained. The experimental analysis of the evaluation of the pressure and temperature in containment vessels at the time of loss of coolant accident is reported. (K.I.)
Availability note (English)
Available from INIS in electronic form and/or on microfiche .Files
29015566.pdf
Files
(254.6 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:b15a59fcc4f73d908c4afd6dea0c2eed
|
254.6 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- PNC-TN--1410-97-028
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29015566
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; CONTAINMENT SHELLS; CONTAINMENT SPRAY SYSTEMS; ECCS; HEAT TRANSFER; JATR REACTOR; LOSS OF COOLANT; PRESSURE GRADIENTS; REACTOR COOLING SYSTEMS; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; CONTAINMENT SYSTEMS; COOLING SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; NATURAL URANIUM REACTORS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS