Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5

Baris Sarikaya, Fatih Alim, Kostadin Ivanov, Kenan Unlu, Jack Brenizer, Yousry Azmy

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)

Abstract

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.

Original languageEnglish (US)
Title of host publicationProceedings of the PHYSOR 2004
Subtitle of host publicationThe Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages2079-2086
Number of pages8
StatePublished - Dec 1 2004
EventPHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States
Duration: Apr 25 2004Apr 29 2004

Publication series

NameProceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Other

OtherPHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
CountryUnited States
CityChicago, IL
Period4/25/044/29/04

Fingerprint

Moderators
Neutron beams
Neutrons
Radiation
Reactor cores
Graphite
Irradiation
Geometry

All Science Journal Classification (ASJC) codes

  • Engineering(all)

Cite this

Sarikaya, B., Alim, F., Ivanov, K., Unlu, K., Brenizer, J., & Azmy, Y. (2004). Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments (pp. 2079-2086). (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).
Sarikaya, Baris ; Alim, Fatih ; Ivanov, Kostadin ; Unlu, Kenan ; Brenizer, Jack ; Azmy, Yousry. / Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5. Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. pp. 2079-2086 (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).
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Sarikaya, B, Alim, F, Ivanov, K, Unlu, K, Brenizer, J & Azmy, Y 2004, Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5. in Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, pp. 2079-2086, PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, Chicago, IL, United States, 4/25/04.

Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5. / Sarikaya, Baris; Alim, Fatih; Ivanov, Kostadin; Unlu, Kenan; Brenizer, Jack; Azmy, Yousry.

Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. p. 2079-2086 (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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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.

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Sarikaya B, Alim F, Ivanov K, Unlu K, Brenizer J, Azmy Y. Modeling of existing beam-port facility at PSU breazeale reactor by using MCNP5. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. p. 2079-2086. (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).