Reactor Fuel Processing

31 books
Spent fuel reprocessing system availability definition by process simulationN Holder
⏱ 1h 20m

Spent fuel reprocessing system availability definition by process simulation

N Holder

197880 pp.
Analysis of spent fuel heatup following loss of water in a spent fuel poolH. P. Nourbakhsh

Analysis of spent fuel heatup following loss of water in a spent fuel pool

H. P. Nourbakhsh

1998No page data
Design study for a 24-cm HTGR microsphere coating furnace / R. R. Suchomel ... [et al.]Oak Ridge National Laboratory. Metals and Ceramics Division.
⏱ 25m

Design study for a 24-cm HTGR microsphere coating furnace / R. R. Suchomel ... [et al.]

Oak Ridge National Laboratory. Metals and Ceramics Division.

197825 pp.
ElcosUnknown Author
⏱ 1h 42m

Elcos

Unknown Author

1996102 pp.
ElcosJean Marie Paratte
⏱ 1h 21m

Elcos

Jean Marie Paratte

199681 pp.
Avtomaticheskoe upravlenie tekhnologicheskimi prot͡sessami radiokhimicheskikh proizvodstvI͡U G Mit͡skevich
⏱ 7h 3m

Avtomaticheskoe upravlenie tekhnologicheskimi prot͡sessami radiokhimicheskikh proizvodstv

I͡U G Mit͡skevich

1970423 pp.
EVAP users manualCarolyn D. Heising
⏱ 45m

EVAP users manual

Carolyn D. Heising

197945 pp.
SIFAIL, a subprogram to calculate cladding deformation and damage for fast reactor fuel pinsD. R. Wilson
⏱ 2h 17m

SIFAIL, a subprogram to calculate cladding deformation and damage for fast reactor fuel pins

D. R. Wilson

1979137 pp.
Actinide processingBrajendra Mishra
⏱ 6h 34m

Actinide processing

Brajendra Mishra

1994394 pp.
Design study for a 24-cm HTGR microshpere coating furnace / R. R. Suchomel ... [et al.]Oak Ridge National Laboratory. Metals and Ceramics Division.
⏱ 25m

Design study for a 24-cm HTGR microshpere coating furnace / R. R. Suchomel ... [et al.]

Oak Ridge National Laboratory. Metals and Ceramics Division.

197825 pp.
Design study for a 24-cm HTGR microshpere coating furnace / R. R. Suchomel ... [et al.]Oak Ridge National Laboratory. Metals and Ceramics Division.
⏱ 25m

Design study for a 24-cm HTGR microshpere coating furnace / R. R. Suchomel ... [et al.]

Oak Ridge National Laboratory. Metals and Ceramics Division.

197825 pp.
A comparative analysis of LWR fuel designsD. L. Acey

A comparative analysis of LWR fuel designs

D. L. Acey

1980No page data
The Marcoule Plutonium Production CenterFrance. Commissariat à l'énergie atomique.
⏱ 1h 0m

The Marcoule Plutonium Production Center

France. Commissariat à l'énergie atomique.

196560 pp.
A new comparative analysis of LWR fuel designsG. M O'Donnell
⏱ 3h 44m

A new comparative analysis of LWR fuel designs

G. M O'Donnell

2001224 pp.
Parusukaramu ni okeru purex purosesu keisan kōdo PULCOKōzō Gonda
⏱ 6h 3m

Parusukaramu ni okeru purex purosesu keisan kōdo PULCO

Kōzō Gonda

1982363 pp.
Valuation of nuclear reactor spent fuel using the HP 67/97 programmable calculatorKenneth A. Solomon
⏱ 41m

Valuation of nuclear reactor spent fuel using the HP 67/97 programmable calculator

Kenneth A. Solomon

197941 pp.
Dvourozměrný výpočet rychlostního pole a vývinu teplotního pole pro kazetu rychlého reaktoru metodou konečných prvkůJ. Schmid
⏱ 25m

Dvourozměrný výpočet rychlostního pole a vývinu teplotního pole pro kazetu rychlého reaktoru metodou konečných prvků

J. Schmid

198525 pp.
CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysisPurdue University. School of Nuclear Engineering.
⏱ 3h 20m

CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysis

Purdue University. School of Nuclear Engineering.

1978200 pp.
Review of nuclear fuel experimental dataJ. Anthony Turnbull
⏱ 1h 7m

Review of nuclear fuel experimental data

J. Anthony Turnbull

199567 pp.
Proceedings of the Seminar on Eurochemic Experience, June 9-11, 1983, Mol, BelgiumSeminar on Eurochemic Experience (1983 Mol, Belgium)
⏱ 3h 44m

Proceedings of the Seminar on Eurochemic Experience, June 9-11, 1983, Mol, Belgium

Seminar on Eurochemic Experience (1983 Mol, Belgium)

1984224 pp.
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