1) Assessment of RELAP5/MOD2, cycle 36.04 against LOFT small break experiment L3-6

Author
Eriksson, J
Series
International agreement report volume NUREG/IA-0033
Publisher
Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Language
English
Formats
Book, Online Content

2) NUREG-0737 technical specifications

Series
Generic letter volume no. 83-36
Generic letter volume no. 83-02
Generic letter volume no. 83-37
More Series...
Publisher
United States Nuclear Regulatory Commission
Language
English
Formats
Book, Online Content

3) Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests

Author
Stubbe, E. J
Series
International agreement report volume NUREG/IA-0034
Publisher
Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Language
English
Formats
Book, Online Content

4) Water coolant technology of power reactors

Author
Cohen, P
Language
English
Book
 Show Editions
On Shelf
2 copies available.
Where is it?

8) LOFT experimental measurements uncertainty analyses

Publisher
Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission
Pub. Date
[1978- ]
Language
English
Book
 Show Editions
On Shelf
2 copies available.
Where is it?
Place Hold

9) Corrosion rate measurements and chemical speciation of corrosion products using thermodynamic modeling of debris components to support GSI-191

Author
Jayin, Vi
Publisher
Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Pub. Date
2005.
Language
English
Formats
Book, Online Content

10) Supercritical-water-cooled reactor

Series
Factsheet
Publisher
Idaho National Laboratory
Pub. Date
[2007?]
Language
English
Formats
Book, Online Content

13) Circumferential cracking in the stainless steel pressurized heater sleeves of pressurized water reactors

Series
NRC information notice volume 2006-27
Publisher
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
Pub. Date
[2006]
Language
English
Formats
Book, Online Content

14) Transmittal of NUREG-0909 relative to the Ginna tube rupture

Series
Generic letter volume no. 82-07
Generic letter volume no. 82-08
Publisher
United States Nuclear Regulatory Commission
Pub. Date
1982.
Language
English
Formats
Book, Online Content

15) Spatial effects and uncertainty analysis for rod ejection accidents in a PWR

Author
Avvakumov, A
Series
International agreement report volume NUREG/IA-0215
Publisher
Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Pub. Date
September 2007.
Language
English
Formats
Book, Online Content

16) Effect of aging on the PWR chemical and volume control system

Author
Grove, E. J
Publisher
Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Pub. Date
1995
Language
English

18) Pressure boundary leakage identified on steam generator bowl drain welds

Series
NRC information notice volume 2005-02
Publisher
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
Pub. Date
[2005]
Language
English
Formats
Book, Online Content

20) Failure to detect freespan cracks in PWR steam generator tubes

Series
NRC information notice volume 2003-05
Publisher
U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
Pub. Date
[2003]
Language
English
Formats
Book, Online Content