PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA

Daniel T. Ingersoll; John E. White; Richard Q. Wright; Hamilton T. Hunter; Charles O. Slater; Robert E. MacFarlane; Norman M. Greene

doi:10.1520/STP15161S

PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA

Daniel T. Ingersoll, John E. White, Richard Q. Wright, Hamilton T. Hunter, Charles O. Slater, Robert E. MacFarlane, Norman M. Greene

Fuel Cycle Analysis

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

Abstract

A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, "pseudo problem-independent" format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data.

Original language	English
Title of host publication	Reactor Dosimetry
Editors	Harry Farrar, E. Parvin Lippincott, John G. Williams, David W. Vehar
Publisher	ASTM International
Pages	660-669
Number of pages	10
ISBN (Electronic)	9780803118997
DOIs	https://doi.org/10.1520/STP15161S
State	Published - 1994
Event	8th ASTM-Euratom Symposium on Reactor Dosimetry - Vail, United States Duration: Aug 29 1993 → Sep 3 1993

Publication series

Name	ASTM Special Technical Publication
Volume	STP 1228
ISSN (Print)	0066-0558

Conference

Conference	8th ASTM-Euratom Symposium on Reactor Dosimetry
Country/Territory	United States
City	Vail
Period	08/29/93 → 09/3/93

Keywords

Nuclear data
cross sections
pressure vessel dosimetry
reactor shielding

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10.1520/STP15161S

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Ingersoll, D. T., White, J. E., Wright, R. Q., Hunter, H. T., Slater, C. O., MacFarlane, R. E., & Greene, N. M. (1994). PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA. In H. Farrar, E. P. Lippincott, J. G. Williams, & D. W. Vehar (Eds.), Reactor Dosimetry (pp. 660-669). (ASTM Special Technical Publication; Vol. STP 1228). ASTM International. https://doi.org/10.1520/STP15161S

Ingersoll, Daniel T. ; White, John E. ; Wright, Richard Q. et al. / PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA. Reactor Dosimetry. editor / Harry Farrar ; E. Parvin Lippincott ; John G. Williams ; David W. Vehar. ASTM International, 1994. pp. 660-669 (ASTM Special Technical Publication).

@inproceedings{23f26db3164f475fb73ef078eff9e540,

title = "PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA",

abstract = "A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, {"}pseudo problem-independent{"} format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data.",

keywords = "Nuclear data, cross sections, pressure vessel dosimetry, reactor shielding",

author = "Ingersoll, {Daniel T.} and White, {John E.} and Wright, {Richard Q.} and Hunter, {Hamilton T.} and Slater, {Charles O.} and MacFarlane, {Robert E.} and Greene, {Norman M.}",

year = "1994",

doi = "10.1520/STP15161S",

language = "English",

series = "ASTM Special Technical Publication",

publisher = "ASTM International",

pages = "660--669",

editor = "Harry Farrar and Lippincott, {E. Parvin} and Williams, {John G.} and Vehar, {David W.}",

booktitle = "Reactor Dosimetry",

}

Ingersoll, DT, White, JE, Wright, RQ, Hunter, HT, Slater, CO, MacFarlane, RE & Greene, NM 1994, PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA. in H Farrar, EP Lippincott, JG Williams & DW Vehar (eds), Reactor Dosimetry. ASTM Special Technical Publication, vol. STP 1228, ASTM International, pp. 660-669, 8th ASTM-Euratom Symposium on Reactor Dosimetry, Vail, United States, 08/29/93. https://doi.org/10.1520/STP15161S

PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA. / Ingersoll, Daniel T.; White, John E.; Wright, Richard Q. et al.
Reactor Dosimetry. ed. / Harry Farrar; E. Parvin Lippincott; John G. Williams; David W. Vehar. ASTM International, 1994. p. 660-669 (ASTM Special Technical Publication; Vol. STP 1228).

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

TY - GEN

T1 - PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA

AU - Ingersoll, Daniel T.

AU - White, John E.

AU - Wright, Richard Q.

AU - Hunter, Hamilton T.

AU - Slater, Charles O.

AU - MacFarlane, Robert E.

AU - Greene, Norman M.

PY - 1994

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N2 - A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, "pseudo problem-independent" format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data.

AB - A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, "pseudo problem-independent" format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data.

KW - Nuclear data

KW - cross sections

KW - pressure vessel dosimetry

KW - reactor shielding

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AN - SCOPUS:85165334585

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A2 - Williams, John G.

A2 - Vehar, David W.

PB - ASTM International

T2 - 8th ASTM-Euratom Symposium on Reactor Dosimetry

Y2 - 29 August 1993 through 3 September 1993

ER -

Ingersoll DT, White JE, Wright RQ, Hunter HT, Slater CO, MacFarlane RE et al. PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA. In Farrar H, Lippincott EP, Williams JG, Vehar DW, editors, Reactor Dosimetry. ASTM International. 1994. p. 660-669. (ASTM Special Technical Publication). doi: 10.1520/STP15161S

PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/BVI NUCLEAR DATA

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