Neutron exposure parameters for the metallurgical test specimens in the sixth heavy-section steel irradiation series
- Oak Ridge National Lab., TN (USA)
The goal of the Heavy-Section Steel Irradiation (HSSI) Program Sixth Irradiation Series is to determine the effect of irradiation on the shape and shift of the crack-arrest toughness versus temperature curve. Two capsules which contained crack-arrest and Charpy V-notch test specimens have been irradiated at the Oak Ridge Research Reactor located at the Oak Ridge National Laboratory. these capsules have been disassembled, internal dosimeters have been analyzed, and exposure parameters are presented for each irradiation test specimen. This report describes the computational methodology for the least-squares presents exposure parameters at each test specimen location for the fluence rate greater than 1.0 MeV, fluence rate greater than 0.1 MeV, and displacements per atom. The specific activity of each dosimeter at the end of irradiation is listed in the Appendix. 10 refs., 8 figs., 4 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7176322
- Report Number(s):
- NUREG/CR-5409; ORNL/TM--11267; ON: TI90010806
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutron exposure parameters for the metallurgical test specimens in the fifth heavy-section steel technology irradiation series capsules
Neutron Exposure Parameters for the Dosimetry Capsule in the Heavy-Section Steel Irradiation Program Tenth Irradiation Series
Results of crack-arrest tests on irradiated a 508 class 3 steel
Technical Report
·
Mon Feb 29 23:00:00 EST 1988
·
OSTI ID:5151188
Neutron Exposure Parameters for the Dosimetry Capsule in the Heavy-Section Steel Irradiation Program Tenth Irradiation Series
Technical Report
·
Thu Oct 01 00:00:00 EDT 1998
·
OSTI ID:1300
Results of crack-arrest tests on irradiated a 508 class 3 steel
Technical Report
·
Sat Jan 31 23:00:00 EST 1998
·
OSTI ID:576023
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CONTAINERS
DATA ANALYSIS
DOSIMETRY
EMBRITTLEMENT
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MECHANICAL PROPERTIES
NEUTRON DOSIMETRY
NEUTRON FLUENCE
PRESSURE VESSELS
RADIATION EFFECTS
STEELS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CONTAINERS
DATA ANALYSIS
DOSIMETRY
EMBRITTLEMENT
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MECHANICAL PROPERTIES
NEUTRON DOSIMETRY
NEUTRON FLUENCE
PRESSURE VESSELS
RADIATION EFFECTS
STEELS