skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Hot Cell Window Shielding Analysis Using MCNP

Abstract

The Idaho National Laboratory Materials and Fuels Complex nuclear facilities are undergoing a documented safety analysis upgrade. In conjunction with the upgrade effort, shielding analysis of the Fuel Conditioning Facility (FCF) hot cell windows has been conducted. This paper describes the shielding analysis methodology. Each 4-ft thick window uses nine glass slabs, an oil film between the slabs, numerous steel plates, and packed lead wool. Operations in the hot cell center on used nuclear fuel (UNF) processing. Prior to the shielding analysis, shield testing with a gamma ray source was conducted, and the windows were found to be very effective gamma shields. Despite these results, because the glass contained significant amounts of lead and little neutron absorbing material, some doubt lingered regarding the effectiveness of the windows in neutron shielding situations, such as during an accidental criticality. MCNP was selected as an analysis tool because it could model complicated geometry, and it could track gamma and neutron radiation. A bounding criticality source was developed based on the composition of the UNF. Additionally, a bounding gamma source was developed based on the fission product content of the UNF. Modeling the windows required field inspections and detailed examination of drawings and materialmore » specifications. Consistent with the shield testing results, MCNP results demonstrated that the shielding was very effective with respect to gamma radiation, and in addition, the analysis demonstrated that the shielding was also very effective during an accidental criticality.« less

Authors:
; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
957516
Report Number(s):
INL/CON-09-15334
TRN: US1000617
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: Safety Analysis Working Group,Los Vegas Nevada,05/08/2009,05/14/2009
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CRITICALITY; FISSION PRODUCTS; GAMMA RADIATION; GAMMA SOURCES; GEOMETRY; GLASS; HOT CELLS; NEUTRONS; NUCLEAR FACILITIES; NUCLEAR FUELS; SAFETY ANALYSIS; SHIELDING; SHIELDS; SPECIFICATIONS; STEELS; TESTING; WINDOWS; WOOL; Criticality; MCNP; shielding

Citation Formats

Chad L. Pope, Wade W. Scates, and J. Todd Taylor. Hot Cell Window Shielding Analysis Using MCNP. United States: N. p., 2009. Web.
Chad L. Pope, Wade W. Scates, & J. Todd Taylor. Hot Cell Window Shielding Analysis Using MCNP. United States.
Chad L. Pope, Wade W. Scates, and J. Todd Taylor. Fri . "Hot Cell Window Shielding Analysis Using MCNP". United States. https://www.osti.gov/servlets/purl/957516.
@article{osti_957516,
title = {Hot Cell Window Shielding Analysis Using MCNP},
author = {Chad L. Pope and Wade W. Scates and J. Todd Taylor},
abstractNote = {The Idaho National Laboratory Materials and Fuels Complex nuclear facilities are undergoing a documented safety analysis upgrade. In conjunction with the upgrade effort, shielding analysis of the Fuel Conditioning Facility (FCF) hot cell windows has been conducted. This paper describes the shielding analysis methodology. Each 4-ft thick window uses nine glass slabs, an oil film between the slabs, numerous steel plates, and packed lead wool. Operations in the hot cell center on used nuclear fuel (UNF) processing. Prior to the shielding analysis, shield testing with a gamma ray source was conducted, and the windows were found to be very effective gamma shields. Despite these results, because the glass contained significant amounts of lead and little neutron absorbing material, some doubt lingered regarding the effectiveness of the windows in neutron shielding situations, such as during an accidental criticality. MCNP was selected as an analysis tool because it could model complicated geometry, and it could track gamma and neutron radiation. A bounding criticality source was developed based on the composition of the UNF. Additionally, a bounding gamma source was developed based on the fission product content of the UNF. Modeling the windows required field inspections and detailed examination of drawings and material specifications. Consistent with the shield testing results, MCNP results demonstrated that the shielding was very effective with respect to gamma radiation, and in addition, the analysis demonstrated that the shielding was also very effective during an accidental criticality.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri May 01 00:00:00 EDT 2009},
month = {Fri May 01 00:00:00 EDT 2009}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: