title: Extending the maximum operation time of the MNSR reactor.
abstract: An effective modification to extend the maximum operation time of the Miniature Neutron Source Reactor (MNSR) to enhance the utilization of the reactor has been tested using the MCNP4C code. This modification consisted of inserting manually in each of the reactor inner irradiation tube a chain of three polyethylene-connected containers filled of water. The total height of the chain was 11.5cm. The replacement of the actual cadmium absorber with B(10) absorber was needed as well. The rest of the core structure materials and dimensions remained unchanged. A 3-D neutronic model with the new modifications was developed to compare the neutronic parameters of the old and modified cores. The results of the old and modified core excess reactivities (ρex) were: 3.954, 6.241 mk respectively. The maximum reactor operation times were: 428, 1025min and the safety reactivity factors were: 1.654 and 1.595 respectively. Therefore, a 139% increase in the maximum reactor operation time was noticed for the modified core. This increase enhanced the utilization of the MNSR reactor to conduct a long time irradiation of the unknown samples using the NAA technique and increase the amount of radioisotope production in the reactor.
authors.affiliation: Nuclear Engineering Department, Atomic Energy Commission, P. O. Box 6091, Damascus, Syria. Electronic address: pscientific9@aec.org.sy.
authors.forename: S
authors.initials: S
authors.lastname: Dawahra
authors.affiliation: Nuclear Engineering Department, Atomic Energy Commission, P. O. Box 6091, Damascus, Syria.
authors.forename: K
authors.initials: K
authors.lastname: Khattab
authors.affiliation: Nuclear Engineering Department, Atomic Energy Commission, P. O. Box 6091, Damascus, Syria.
authors.forename: G
authors.initials: G
authors.lastname: Saba
keywords: MCNP4C code; MNSR; Operation time; Safety reactivity factor; The excess reactivity