Published August 1984 | Version v1
Report Restricted

Statistical evaluation of the metallurgical test data in the ORR-PSF-PVS irradiation experiment

Creators

Description

A statistical analysis of Charpy test results of the two-year Pressure Vessel Simulation metallurgical irradiation experiment was performed. Determination of transition temperature and upper shelf energy derived from computer fits compare well with eyeball fits. Uncertainties for all results can be obtained with computer fits. The results were compared with predictions in Regulatory Guide 1.99 and other irradiation damage models

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - GPO as TI84015221.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
34 p.
Report number
NUREG/CR--3815

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16049621
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; EMBRITTLEMENT; NEUTRON FLUENCE; ORR REACTOR; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR MATERIALS; STEEL-MNMO; STEEL-MNNIMO; TESTING
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATERIALS; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ORNL/TM--9207.