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1

Comprehensive Nuclear Materials, Volume 3: Advanced Fuels / Fuel Cladding / Nuclear Fuel Performance Modeling and Simulation
R.J.M. Konings (Editor)
2

Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
United States. Dept. of Energy. Yucca Mountain Project Office.; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information
3

Handbook of Nuclear Engineering
Dan Gabriel Cacuci
4

Nuclear Fuel Behavior Modelling at High Burnup (and exper support) (IAEA TECDOC-1233)
5

Fission Gas Release, Fuel Rod Chem Related to Extended Burnup (IAEA TECDOC-697)
6

Water Reactor Fuel Element Modeling at High Burnup (IAEA TECDOC-0957)
7

Nuclear Materials
B.R.T. Frost (Editor)
8

Adv in Fuel-Pellet Tech for Imprvd Perf at High Burnup (IAEA TECDOC-1036)
9

Sensitivity, Parametric Evals - Burnup Credit for Spent Nuclear Fuel Packages
10

Tech, Economic Limits to Fuel Burnup Extension (IAEA TECDOC-1299)
11

Storage of Spent Fuel from Power Reactors (IAEA TECDOC-1089)
12

Comprehensive Nuclear Materials, Volume 2: Material Properties / Oxide Fuels for Light Water Reactors and Fast Neutron Reactors
R.J.M. Konings (editor)
13

Review of Tech Issues Related to Burnup Credit for LWR Fuel
14

Fast Breeder Reactors. Proceedings of the London Conference on Fast Breeder Reactors Organized by the British Nuclear Energy Society, 17th–19th May 1966
P. V. Evans (Eds.)
15

TopFuel'97 : proceedings of the conference organized by the British Nuclear Energy Society and held in Manchester on 9-11 June 1997
coll.
16

Research Reactor Conversion [to Low-Enriched Uranium Fuels] (IAEA TECDOC-233)
17

Management of spent fuel from nuclear power reactors : proceedings of an international conference on spent fuel from nuclear power reactors
International Atomic Energy Agency.; OECD Nuclear Energy Agency
18

Parametric study of the effect of burnable poison rods for PWR burnup credit
J C Wagner; C V Parks; Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness
19

Physics of Nuclear Reactors
Unknown
20

Research Reactor Core Conversion Guidebook Vol 4 [Fuels] (IAEA TECDOC-643v4)
21

U Uranium: Behavior of Uranium Fuels in Nuclear Reactors. Reprocessing of Spent Nuclear Fuels
Helmut Aßmann; Erich Merz; Aristides Naoumidis; Hubertus Nickel; Heinz Stehle; Gilbert N. Walton (auth.); Karl-Christian Buschbeck; Cornelius Keller (eds.)
22

The Radiochemistry of Nuclear Power Plants with Light Water Reactors
Karl-Heinz Neeb
23

The radiochemistry of nuclear power plants with light water reactors
Neeb; Karl-Heinz
24

Technical aspects of high converter reactors : proceedings of a Technical Committee meeting held in Nuremberg, 26-29 March 1990
International Atomic Energy Agency
25

Introduction to nuclear reactor physics
Masterson; Robert
26

Recycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995
International Atomic Energy Agency. Technical Committee on Recycling of Plutonium and Uranium in Water Reactor Fuel
27

Status of Fast Reactor Research and Technology Development
28

Fuel Modelling at Extended Burnup (IAEA TECDOC-998)
29

Thorium fuel utilization : options and trends : proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999
International Atomic Energy Agency
30

Super Light Water Reactors and Super Fast Reactors: Supercritical-Pressure Light Water Cooled Reactors
Yoshiaki Oka; Seiichi Koshizuka; Yuki Ishiwatari; Akifumi Yamaji
31

Nuclear fuel safety criteria technical review
OECD
32

Fuel Safety Criteria - Tech Review (csni-r99-25)
33

Nuclear Materials for Fission Reactors
H. Matzke and G. Schumacher (Eds.)
34

Deep-Burn Modular Helium Reactor Fuel Development Plan
D McEachern; ORNL
35

The physics problems in thermal reactor design proceedings of an international conference at the Institution of Civil Engineers, London SWl, 27-29 June 1967
36

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application - Methodology to Construct Burnup Profile of Fuel Pebbles in PBR
Tang; Yushi; Zhang; Liguo; Guo; Qiuju; Cao; Jianzhu; Tong; Jiejuan
37

Emerging Nuclear Energy, Transmutation Systems - Core Physics, Eng. Concepts (IAEA TECDOC-1356)