Name: ANS 19.10 : 2009(R2016)
Brand: ANS

METHODS FOR DETERMINING NEUTRON FLUENCE IN BWR AND PWR PRESSURE VESSEL AND REACTOR INTERNALS

Superseded date

20-10-2022

Published date

12-01-2013

Publisher

American Nuclear Society

Pertains to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs).

ANS 19.3 : 2011(R2017)	STEADY-STATE NEUTRONICS METHODS FOR POWER REACTOR ANALYSIS
ANS 19.6.1 : 2011(R2016)	RELOAD STARTUP PHYSICS TESTS FOR PRESSURIZED WATER REACTORS
ANS 19.3.4 : 2002(R2017)	THE DETERMINATION OF THERMAL ENERGY DEPOSITION RATES IN NUCLEAR REACTORS
ISO 19226:2017	Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
BS ISO 19226:2017	Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
17/30337935 DC : 0	BS ISO 19226 - NUCLEAR ENERGY - DETERMINATION OF NEUTRON FLUENCE AND DISPLACEMENTS PER ATOM (DPA) IN REACTOR VESSEL AND INTERNALS

ANS 19.1 : 2002(R2011)	NUCLEAR DATA SETS FOR REACTOR DESIGN CALCULATIONS
ANS 19.3.4 : 2002(R2017)	THE DETERMINATION OF THERMAL ENERGY DEPOSITION RATES IN NUCLEAR REACTORS
ANS 5.1 : 2014	DECAY HEAT POWER IN LIGHT WATER REACTORS
ANS 19.3 : 2011(R2017)	STEADY-STATE NEUTRONICS METHODS FOR POWER REACTOR ANALYSIS
ANS 19.5 : 1995	REQUIREMENTS FOR REFERENCE REACTOR PHYSICS MEASUREMENTS
ANS 19.4 : 2017	A GUIDE FOR ACQUISITION AND DOCUMENTATION OF REFERENCE POWER REACTOR PHYSICS MEASUREMENTS FOR NUCLEAR ANALYSIS VERIFICATION
ANS 19.11 : 2017	CALCULATION AND MEASUREMENT OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR PRESSURIZED WATER REACTORS
ANS 19.6.1 : 2011(R2016)	RELOAD STARTUP PHYSICS TESTS FOR PRESSURIZED WATER REACTORS

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