Analysis of proposed gamma-ray detection system for the monitoring of core water inventory in a pressurized water reactor
Description
An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and downcomer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport path, and the relative void fraction in different water regions) on the detector response are studied. The calculational results have been validated by a favorable comparison with LOFT experimental data. Within the limitations and approximations considered in the analysis, the results indicate that the gamma-ray detection scheme is able to unambiguously respond to changes in the coolant inventory within any vessel water region
Availability note (English)
Available from NTIS, PC A10/MF A01; 1 as DE88005785.Files
19073236.pdf
Files
(3.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:0a2fc712fb1a0d8ab12d9b9a5f088dd9
|
3.6 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 212 p.
- Report number
- ANL--87-29
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19073236
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ATTENUATION; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; GAMMA DETECTION; LOFT REACTOR; LOSS OF COOLANT; NEUTRON FLUX; PRESSURIZERS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR MONITORING SYSTEMS; REACTOR SAFETY; SOURCE TERMS; THEORETICAL DATA; VOID FRACTION; VOIDS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DATA; DETECTION; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; RADIATION DETECTION; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.