27.120.10 : Reactor engineering

ASTM E185-16

ASTM E185-16

Superseded Historical

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

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ASTM E2215-16

ASTM E2215-16

Superseded Historical

Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

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BS 4877:2016

BS 4877:2016

Superseded Historical

Nuclear reactor instrumentation and control. Code of practice

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ASTM E521-16

ASTM E521-16

Superseded Historical

Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation

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ASTM E798-16

ASTM E798-16

Superseded Historical

Standard Practice for Conducting Irradiations at Accelerator-Based Neutron Sources

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ASTM E2006-16

ASTM E2006-16

Superseded Historical

Standard Guide for Benchmark Testing of Light Water Reactor Calculations

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DIN 25457-6:2015-11

DIN 25457-6:2015-11

Superseded Historical

Activity measurement methods in the clearance of radioactive waste substances and nuclear facility components - Part 6: Rubble and buildings

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ASTM E185-15

ASTM E185-15

Superseded Historical

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

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ASTM E2215-15

ASTM E2215-15

Superseded Historical

Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

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ASTM E185-15e1

ASTM E185-15e1

Superseded Historical

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

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ASTM D7013/D7013M-15

ASTM D7013/D7013M-15

Superseded Historical

Standard Guide for Calibration Facility Setup for Nuclear Surface Gauges

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ASTM E900-15e1

ASTM E900-15e1

Superseded Historical

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

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ASTM E900-15e2

ASTM E900-15e2

Superseded Historical

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

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ASTM E900-15

ASTM E900-15

Superseded Historical

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

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ASTM C1533-15

ASTM C1533-15

Superseded Historical

Standard Guide for General Design Considerations for Hot Cell Equipment

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