TY - GEN
T1 - Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5
AU - Sarikaya, Baris
AU - Alim, Fatih
AU - Ivanov, Kostadin
AU - Unlu, Kenan
AU - Brenizer, Jack
AU - Azmy, Yousry
PY - 2004
Y1 - 2004
N2 - The Radiation Science and Engineering Center facilities at the Pennsylvania State University (PSU) include the Penn State Breazeale Reactor, gamma irradiation facilities, and various radiation detection and measurement laboratories. Due to inherited design issues with the current arrangement of beam ports and reactor core-moderator assembly, the development of innovative experimental facilities utilizing neutron beams is extremely limited. Therefore, a new core-moderator location in PSBR pool and beam port geometry was needed to be developed. A study is underway with the support of DOE-INIE funds to examine the existing beam ports for neutron output and to investigate new moderator arid beam-port designs to produce more useful neutron beams. The overall system for this study consists of two major parts, the core model and beam port model. Core calculations are performed by using a three dimensional nodal diffusion code ADMARC-H. Beam port calculations are performed with the MCNP code. An interface program has been developed at PSU to link the diffusion code to the neutron transport code. The MCNP model consists of the D 2O tank, graphite reflector block, and beam port tube with their surroundings. The results of the PSU package show good agreement with the experimental data.
AB - The Radiation Science and Engineering Center facilities at the Pennsylvania State University (PSU) include the Penn State Breazeale Reactor, gamma irradiation facilities, and various radiation detection and measurement laboratories. Due to inherited design issues with the current arrangement of beam ports and reactor core-moderator assembly, the development of innovative experimental facilities utilizing neutron beams is extremely limited. Therefore, a new core-moderator location in PSBR pool and beam port geometry was needed to be developed. A study is underway with the support of DOE-INIE funds to examine the existing beam ports for neutron output and to investigate new moderator arid beam-port designs to produce more useful neutron beams. The overall system for this study consists of two major parts, the core model and beam port model. Core calculations are performed by using a three dimensional nodal diffusion code ADMARC-H. Beam port calculations are performed with the MCNP code. An interface program has been developed at PSU to link the diffusion code to the neutron transport code. The MCNP model consists of the D 2O tank, graphite reflector block, and beam port tube with their surroundings. The results of the PSU package show good agreement with the experimental data.
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M3 - Conference contribution
AN - SCOPUS:22344443580
SN - 0894486837
SN - 9780894486838
T3 - Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
SP - 2079
EP - 2086
BT - Proceedings of the PHYSOR 2004
T2 - PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Y2 - 25 April 2004 through 29 April 2004
ER -