Published 1978 | Version v1
Report Restricted

Status of the Qualification Testing Evaluation (QTE) Program

Description

The objectives of the Qualification Testing Evaluation (QTE) Program, under the sponsorship of the Office of Water Reactor Safety Research, USNRC, are to obtain data needed for confirmation of the suitability of current standards and Regulatory Guides for Class 1E safety-related equipment and to obtain data that will provide an improved technical basis for modifications of these standards and guides where appropriate. The specific major tasks of the research are: (1) Provide assessments of LOCA testing methodologies including qualitative assessment of the synergistic effects resulting from the combined environments testing of representative Class 1E equipment, (2) Determine the nuclear source term signature for the design-basis LOCA and evaluate the adequacy of radiation simulators, and (3) Provide a model that can be used to simulate the natural aging process of representative Class 1E materials by accelerated aging methods. Each of these tasks has the potential for significant impact on the nuclear power industry. Progress in each is reported

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
SAND--78-1884C

Conference

Title
6. water reactor safety research meeting.
Dates
6 - 9 Nov 1978.
Place
Germantown, MD, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10448766
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; ELECTRICAL EQUIPMENT; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; RESEARCH PROGRAMS; SPECIFICATIONS; TESTING
Descriptors DEC
ACCIDENTS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-781146--3.