NGS Activity cont'd - doe-tsl-4-20060097

DOE-TSL-4-2006

APPENDIX C

NGS Activity

ANS TJC

Technical Journals Committee

ANS -1

Performance of Critical Experiments

ANS -3.11

Determining Meteorological Information at Nuclear Facility

Installations

ANS -5.1

Decay Heat Power in Light Water Reactors

ANS -6

Radiation Protection and Shielding

ANS -8

Fissionable Material Outside Reactors

ANS -8.1

Nuclear Criticality Safety in Operations with Fissionable

Materials Outside Reactors

ANS -8.3

Criticality Accident Alarm System

ANS -8.7

Guide for Nuclear Criticality Safety in the Storage of

Fissile Materials

ANS -8.12

Nuclear Criticality Cont rol and Safety of Plutonium-

Uranium Fuel Mixtures Outside Reactors

ANS -8.14

Use of Solutions of Neutron Absorbers for Criticality

ANS -8.15

Nuclear Criticality Control of Special Actinide Elements

ANS -8.20

Nuclear Criticality Safety Training

ANS -8.21

Use of Fixed Neutron Absorbers in the Design of Nuclear

Facilities Outside Reactors

ANS -8.22

Nuclear Criticality Safety Based on Limited and Controlled

Moderation

ANS -8.23

Criticality Accident Emergency Planning & Response

ANS -8.24

Criticality Code Validation

ANS -8.25

Posting Standard

ANS -10

Mathematics and Computation

ANS -10.4

Guidelines for the Verification and Validation of Scientific

and Engineering Computer Programs for the Nuclear Industry

ANS -15

Operation of Research Reactors

ANS -15.4

Selection/Tr aining of Personnel

ANS -15.11

Radiological Control at Research Reactor Facilities

ANS -15.16

Emergency Planning for Research Reactors

ANS -16.1

Measurement of the Leachability of Solidified Low-Level

Radioactive Wastes by a Short -Term Test Procedure

ANS -19

Physics of Reactor Design

ANS -19.8

Fission Product Chain Yields

C- 11