Development and testing of ENDF/B-VI. 8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6 / prepared by D. Wiarda [and others].

Format:

Book

Government document

Contributor:

Wiarda, Dorothea

U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards

U.S. Nuclear Regulatory Commission. Division of Spent Fuel Storage and Transportation

Oak Ridge National Laboratory

Language:

English

Subjects (All):

Criticality (Nuclear engineering).

Nuclear power plants--United States--Shielding (Radiation)--Data processing.

Nuclear power plants.

Nuclear power plants--United States--Shielding (Radiation)--Computer programs.

Nuclear reactors--United States--Shielding (Radiation)--Data processing.

Nuclear reactors.

Nuclear reactors--Shielding (Radiation)--United States--Computer programs.

Neutron cross section standards--Databases.

Neutron cross section standards.

Neutron cross section standards--Computer programs.

Nuclear reactors--Shielding (Radiation)--Computer programs.

Nuclear reactors--Shielding (Radiation)--Data processing.

United States.

Genre:

databases.

Databases.

Physical Description:

1 online resource (140 pages) : illustrations (chiefly color)

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, [2009]

Notes:

Title from PDF title screen (viewed on Apr. 16, 2010).

"Date published: February 2009."

Performing organization: Oak Ridge National Laboratory.

"NUREG/CR-6990."

"ORNL/TM-2008/047."

Includes bibliographical references (pages 89-90).

Other Format:

Print version: Development and testing of ENDF/B-VI. 8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6.

OCLC:

607562127