Study of the bubble-void distribution effect on reactivity in the MNSR research reactor
Creators
- 1. Atomic Energy Commission, Damascus (Syrian Arab Republic), Dept. of Nuclear Engineering
Description
In this work, the effect of void on reactivity in the MNSR core has been studied, where void was represented as a localized vapor bubble moving within the core coolant. The effect of void on reactivity, in both axial and radial directions, was determined. An average void coefficient was calculated and found to be 4.57689 mk/%. Since neither measured nor published data are available on void coefficients in MNSR, comparison was not possible. However, the current calculated results seem acceptable and agree with the physical sense. Moreover, space-distribution of thermal neutron flux in all regions of the reactor has been obtained. As a result, a map of this flux distribution has been made. The map gives a clear picture on the neutron flux distribution through out various components of the MNSR. Two neutronics codes have been used in this analysis: WIMSD4 and CITATION. WIMSD4 was used to generate macroscopic cross sections for all materials in the reactor i.e. unit cell calculations, whereas the CITATION code was used for reactor core calculation. Finally, the effect of moderator density reduction on neutron flux spectrum has been calculated too. (Authors)
Additional details
Publishing Information
- Journal Title
- Aalam Al-Zarra
- Journal Issue
- 104
- Journal Page Range
- p. 66
- ISSN
- 1607-985X
INIS
- Country of Publication
- Syrian Arab Republic
- Country of Input or Organization
- Syrian Arab Republic
- INIS RN
- 37085527
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUBBLES; C CODES; CALCULATION METHODS; MNSR TYPE REACTORS; NEUTRON FLUX; NEUTRON SPECTRA; REACTIVITY COEFFICIENTS; REACTOR CORES; VOID COEFFICIENT; W CODES
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; RADIATION FLUX; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPECTRA; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Abstract of Scientific Research