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ASTM Selected Technical Papers
Reactor Dosimetry
By
H Farrar, IV IV
H Farrar, IV IV
1
Symposium General Chairman Consultant Bell Canyon, California
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EP Lippincott
EP Lippincott
2
Program Committee Chairman
?
Westinghouse
?
Pittsburgh, Pennsylvania
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JG Williams
JG Williams
3
Program Committee Vice Chairman
?
University of Arizona
?
Tucson, Arizona
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DW Vehar
DW Vehar
4
Scientific Secretary
?
Sandia National Laboratories
?
Albuquerque, New Mexico
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ISBN-10:
0-8031-1899-6
ISBN:
978-0-8031-1899-7
No. of Pages:
131
Publisher:
ASTM International
Publication date:
1994

The objective of this research was to determine improved thermal, epithermal, and fast fluxes and several responses at mechanical test surveillance location keys 2, 4, 5, and 7 of the pressure vessel of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) for the beginning of the fuel cycle. The purpose of the research was to provide essential flux data in support of radiation embrittlenient studies of the pressure vessel shell and beam tubes at some of the important locations.

1.
Pamphlet titled “High Flux Isotope Reactor”, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6387,
07
1991
.
2.
Ford
W.E.
,et al
, “
ANSL-V: ENDF/B-V Baaed Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies
,”
Oak Ridge National Lab
, ORNL-6618,
1990
.
3.
Primm
R.T.
 III
, “
Reactor Physics Input to the Safety Analysis Report for the High Flux Isotope Reactor
”,
Oak Ridge National Lab
, ORNL/TM-11956,
10
1991
.
4.
Engle
W.W.
, RZ Base Case, Shielding Input to the HFIR SAR, EPM.HFIR.91.001,
06
1991
.
5.
Greene
N.M.
,et al
, “
AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross-Section Libraries form ENDF/B-IV and/or ENDF/B-V⩽
\rd,
Oak Ridge National Lab
, ORNL/CSD/TM-283,
10
1992
.
6.
Rhoades
W.A.
and
Childs
R.L.
. “
The DORT Two-Dimensional Discrete Ordinates Transport Code
, ”
Nucl. Sci. & Engr
.
99
,
1
,88–89,
05
1988
.
7.
Rhoades
W.A.
, et al
, “
Vehicle Code System (VCS) User's Manual
”,
Oak Ridge National Lab
,ORNL-TM-4648,
08
1974
.
8.
Thompson
J.L.
, et al
, “
Development and Evaluation of DOTTOR, a Computer Code to Couple Two-Dimensional to Three-Dimensional Discrete Ordinates Calculations
”,
Oak Ridge National Lab
,ORNL/TM-9919,
1986
.
9.
Rhoades
W.A.
and
Childs
R.L.
, “
The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code
”,
Oak Ridge National Lab
,ORNL-6268,
11
1987
.
10.
Childs
R.L.
,
Rhoades
W.A.
, and
Williams
L.R.
, “
Three-Dimensional Calculations of Neutron Streaming in the Beam Tubes of the ORNL HFIR Reactor
”, Proceedings, 7th International Conference on Radiation Shielding, VOL
II
,
09
1988
.
11.
The ELXSIR Cross-Section Library for LWR Pressure Vessel Irradiation Studies: Part of the LEPRICON Computer Code System
”,
Oak Ridge National Lab
,EPRI NP-3654,
1984
.
12.
SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation
,” NUREG/CR-0200 Rev. 4(ORNL/NUREG/CSD-2/R4) Excerpts from Vols.
I
,
II
, and
III
, (Draft
03
1992
).
13.
Remic
,
I.
,
Kam
,
F.
, “
HFIR Neutron Spectra Determination
”, DRAFT NUREG (
23
03
1993
).
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