MCNPX VS. DORT for SNS shielding design studies

Irina I. Popova

MCNPX VS. DORT for SNS shielding design studies

Research output: Contribution to conference › Paper › peer-review

Abstract

A comparison of radiation transport through the 18-meter-long access way adjacent to the Spallation Neutron Source accelerator tunnel and 2.2-meter-thick massive shielding door which closes the access way was performed using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for the door to study radiation penetration. Analyses show that the results from the two methods are in good agreement.

Original language	English
Pages	647-653
Number of pages	7
State	Published - 2005
Externally published	Yes
Event	Monte Carlo 2005 Topical Meeting - Chattanooga, TN, United States Duration: Apr 17 2005 → Apr 21 2005

Conference

Conference	Monte Carlo 2005 Topical Meeting
Country/Territory	United States
City	Chattanooga, TN
Period	04/17/05 → 04/21/05

Keywords

Accelerator
Shielding

Cite this

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title = "MCNPX VS. DORT for SNS shielding design studies",

abstract = "A comparison of radiation transport through the 18-meter-long access way adjacent to the Spallation Neutron Source accelerator tunnel and 2.2-meter-thick massive shielding door which closes the access way was performed using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for the door to study radiation penetration. Analyses show that the results from the two methods are in good agreement.",

keywords = "Accelerator, Shielding",

author = "Popova, {Irina I.}",

year = "2005",

language = "English",

pages = "647--653",

note = "Monte Carlo 2005 Topical Meeting ; Conference date: 17-04-2005 Through 21-04-2005",

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TY - CONF

T1 - MCNPX VS. DORT for SNS shielding design studies

AU - Popova, Irina I.

PY - 2005

Y1 - 2005

N2 - A comparison of radiation transport through the 18-meter-long access way adjacent to the Spallation Neutron Source accelerator tunnel and 2.2-meter-thick massive shielding door which closes the access way was performed using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for the door to study radiation penetration. Analyses show that the results from the two methods are in good agreement.

AB - A comparison of radiation transport through the 18-meter-long access way adjacent to the Spallation Neutron Source accelerator tunnel and 2.2-meter-thick massive shielding door which closes the access way was performed using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for the door to study radiation penetration. Analyses show that the results from the two methods are in good agreement.

KW - Accelerator

KW - Shielding

UR - http://www.scopus.com/inward/record.url?scp=33644585669&partnerID=8YFLogxK

M3 - Paper

AN - SCOPUS:33644585669

SP - 647

EP - 653

T2 - Monte Carlo 2005 Topical Meeting

Y2 - 17 April 2005 through 21 April 2005

ER -

MCNPX VS. DORT for SNS shielding design studies

Abstract

Conference

Keywords

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