On scale validation for PBR analysis

Germina Ilas

On scale validation for PBR analysis

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

4 Scopus citations

Abstract

Studies were performed to assess the capabilities of the SCALE code system to provide accurate cross sections for analyses of pebble bed reactor configurations. The analyzed configurations are representative of fuel in the HTR-10 reactor in the first critical core and at full power operation conditions. Relevant parameters-multiplication constant, spectral indices, few-group cross sections-are calculated with SCALE for the considered configurations. The results are compared to results obtained with corresponding consistent MCNP models. The code-to-code comparison shows good agreement at both room and operating temperatures, indicating a good performance of SCALE for analysis of doubly heterogeneous fuel configurations.

Original language	English
Title of host publication	International Conference on the Physics of Reactors 2010, PHYSOR 2010
Publisher	American Nuclear Society
Pages	1202-1211
Number of pages	10
ISBN (Print)	9781617820014
State	Published - 2010
Event	International Conference on the Physics of Reactors 2010, PHYSOR 2010 - Pittsburgh, United States Duration: May 9 2010 → May 14 2010

Publication series

Name	International Conference on the Physics of Reactors 2010, PHYSOR 2010
Volume	2

Conference

Conference	International Conference on the Physics of Reactors 2010, PHYSOR 2010
Country/Territory	United States
City	Pittsburgh
Period	05/9/10 → 05/14/10

Keywords

Cross sections
HTR-10
MCNP
Pebble bed reactor
SCALE

Cite this

@inproceedings{fb8c21bd11f24deaace53934cd35619b,

title = "On scale validation for PBR analysis",

abstract = "Studies were performed to assess the capabilities of the SCALE code system to provide accurate cross sections for analyses of pebble bed reactor configurations. The analyzed configurations are representative of fuel in the HTR-10 reactor in the first critical core and at full power operation conditions. Relevant parameters-multiplication constant, spectral indices, few-group cross sections-are calculated with SCALE for the considered configurations. The results are compared to results obtained with corresponding consistent MCNP models. The code-to-code comparison shows good agreement at both room and operating temperatures, indicating a good performance of SCALE for analysis of doubly heterogeneous fuel configurations.",

keywords = "Cross sections, HTR-10, MCNP, Pebble bed reactor, SCALE",

author = "Germina Ilas",

year = "2010",

language = "English",

isbn = "9781617820014",

series = "International Conference on the Physics of Reactors 2010, PHYSOR 2010",

publisher = "American Nuclear Society",

pages = "1202--1211",

booktitle = "International Conference on the Physics of Reactors 2010, PHYSOR 2010",

note = "International Conference on the Physics of Reactors 2010, PHYSOR 2010 ; Conference date: 09-05-2010 Through 14-05-2010",

}

TY - GEN

T1 - On scale validation for PBR analysis

AU - Ilas, Germina

PY - 2010

Y1 - 2010

N2 - Studies were performed to assess the capabilities of the SCALE code system to provide accurate cross sections for analyses of pebble bed reactor configurations. The analyzed configurations are representative of fuel in the HTR-10 reactor in the first critical core and at full power operation conditions. Relevant parameters-multiplication constant, spectral indices, few-group cross sections-are calculated with SCALE for the considered configurations. The results are compared to results obtained with corresponding consistent MCNP models. The code-to-code comparison shows good agreement at both room and operating temperatures, indicating a good performance of SCALE for analysis of doubly heterogeneous fuel configurations.

AB - Studies were performed to assess the capabilities of the SCALE code system to provide accurate cross sections for analyses of pebble bed reactor configurations. The analyzed configurations are representative of fuel in the HTR-10 reactor in the first critical core and at full power operation conditions. Relevant parameters-multiplication constant, spectral indices, few-group cross sections-are calculated with SCALE for the considered configurations. The results are compared to results obtained with corresponding consistent MCNP models. The code-to-code comparison shows good agreement at both room and operating temperatures, indicating a good performance of SCALE for analysis of doubly heterogeneous fuel configurations.

KW - Cross sections

KW - HTR-10

KW - MCNP

KW - Pebble bed reactor

KW - SCALE

UR - https://www.scopus.com/pages/publications/79952406756

M3 - Conference contribution

AN - SCOPUS:79952406756

SN - 9781617820014

T3 - International Conference on the Physics of Reactors 2010, PHYSOR 2010

SP - 1202

EP - 1211

BT - International Conference on the Physics of Reactors 2010, PHYSOR 2010

PB - American Nuclear Society

T2 - International Conference on the Physics of Reactors 2010, PHYSOR 2010

Y2 - 9 May 2010 through 14 May 2010

ER -

On scale validation for PBR analysis

Abstract

Publication series

Conference

Keywords

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