Nuclear Reactors Cooling

452 books
Gas Cooled Reactor Design and Safety (Technical Reports Series (International Atomic Energy Agency))International Atomic Energy Agency.
⏱ 3h 54m

Gas Cooled Reactor Design and Safety (Technical Reports Series (International Atomic Energy Agency))

International Atomic Energy Agency.

1990234 pp.
Development of the LOFT prototype drag screenJames R. Fincke
⏱ 47m

Development of the LOFT prototype drag screen

James R. Fincke

197847 pp.
The failed promise of nuclear powerIrvin C. Bupp
⏱ 4h 1m

The failed promise of nuclear power

Irvin C. Bupp

1978241 pp.
Sodium-cooled fast reactor engineeringSymposium on Progress in Sodium-Cooled Fast Reactor Engineering Monaco 1970.
⏱ 15h 57m

Sodium-cooled fast reactor engineering

Symposium on Progress in Sodium-Cooled Fast Reactor Engineering Monaco 1970.

1970957 pp.
Comparison of containment systems for large sodium-cooled breeder reactorsS. E Seeman
⏱ 3h 17m

Comparison of containment systems for large sodium-cooled breeder reactors

S. E Seeman

1978197 pp.
A criterion for the onset of quench for low flow refloodY. Y Hsu
⏱ 28m

A criterion for the onset of quench for low flow reflood

Y. Y Hsu

198228 pp.
Code and model extensions of the THATCH code for modular high temperature gas-cooled reactorsP. G. Kroger
⏱ 36m

Code and model extensions of the THATCH code for modular high temperature gas-cooled reactors

P. G. Kroger

199336 pp.
COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow testsK. L. Basehore
⏱ 32m

COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow tests

K. L. Basehore

197932 pp.
COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow testsK. L Basehore
⏱ 32m

COBRA-IV comparison with the Ward 11:1 scale LMFBR air flow tests

K. L Basehore

197932 pp.
Okhlazhdenie ėlementov i͡a︡dernykh reaktorov stekai͡u︡shchimi plenkamiB. G. Ganchev
⏱ 3h 10m

Okhlazhdenie ėlementov i͡a︡dernykh reaktorov stekai͡u︡shchimi plenkami

B. G. Ganchev

1987190 pp.
Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3M. Dabrowski
⏱ 3h 35m

Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3

M. Dabrowski

2014215 pp.
Shibia akushidento-ji kakunō yōkinai tajigen netsu ryūdō oyobi FP kyodō kaisekiGenshiryoku Anzen Kiban Kikō

Shibia akushidento-ji kakunō yōkinai tajigen netsu ryūdō oyobi FP kyodō kaiseki

Genshiryoku Anzen Kiban Kikō

2009No page data
Shibia akushidento-ji genshiro reikyakukeinai tajigen netsu ryūdō oyobi FP kyodō kaisekiGenshiryoku Anzen Kiban Kikō

Shibia akushidento-ji genshiro reikyakukeinai tajigen netsu ryūdō oyobi FP kyodō kaiseki

Genshiryoku Anzen Kiban Kikō

2009No page data
Regulation of nuclear powerElizabeth S. Rolph
⏱ 1h 28m

Regulation of nuclear power

Elizabeth S. Rolph

197788 pp.
A review and evaluation of available critical experiment-data for HTGR-non-proliferation fuel cyclesA. M. Baxter
⏱ 35m

A review and evaluation of available critical experiment-data for HTGR-non-proliferation fuel cycles

A. M. Baxter

197735 pp.
GCFR fuel cycle information for the ORNL nonproliferation studyK. J. Baylor
⏱ 2h 35m

GCFR fuel cycle information for the ORNL nonproliferation study

K. J. Baylor

1978155 pp.
Natural circulation cooling in U.S. pressurized water reactorsP. R. McHugh
⏱ 2h 15m

Natural circulation cooling in U.S. pressurized water reactors

P. R. McHugh

1992135 pp.
GCFR fuel cycle information for the ORNL nonproliferation studyK. J Baylor
⏱ 2h 35m

GCFR fuel cycle information for the ORNL nonproliferation study

K. J Baylor

1978155 pp.
A numerical simulation of heat transfer in evaporative cooling towersDudley J. Benton
⏱ 33m

A numerical simulation of heat transfer in evaporative cooling towers

Dudley J. Benton

198333 pp.
Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24Kyu-Soo Kim
⏱ 1h 21m

Assessment of RELAP5/MOD2 critical flow model using Marviken test data 15 and 24

Kyu-Soo Kim

199281 pp.
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