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Journal Articles

Research on the Application of F en for Environmentally Assisted Fatigue Evaluation of the Austenitic SS Pipe Under Combined Transient Loads

Bingbing Liang, Xu Zhang, Haifeng Yin, Yang Dai

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041009.

Paper No: NERS-17-1232

DOI: https://doi.org/10.1115/1.4040368

Published Online: September 10, 2018

... Regulatory issues Codes Plant construction Plant components Plant structures Maintenance Engineering Modifications Life Cycle Extensive testing had proven that reactor coolant environment had significant effects on the fatigue life of materials. Two methods to account for the influence...

View Article titled, Research on the Application of F en for Environmentally Assisted Fatigue Evaluation of the Austenitic SS Pipe Under Combined Transient Loads

Topics: Design, Fatigue, Pipes, Stress, Transients (Dynamics), Electric arc furnaces, Water, Temperature, Pressure

Journal Articles

Planning the Selection and Assignment of Security Forensics Countermeasures

Edita Bajramovic, Jürgen Bochtler, Ines Ben Zid, Andreas Lainer

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041008.

Paper No: NERS-17-1216

DOI: https://doi.org/10.1115/1.4040650

Published Online: September 10, 2018

... online September 10, 2018. Assoc. Editor: John F. P. de Grosbois. 29 10 2017 13 06 2018 Instrumentation Nuclear safety Standards Licensing Regulatory issues Codes Security The international standards are used to explicitly demonstrate that the results to be produced...

View Article titled, Planning the Selection and Assignment of Security Forensics Countermeasures

Topics: Forensic sciences, Security

Journal Articles

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Jian Li, Ding She, Lei Shi

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021007.

Paper No: NERS-17-1089

DOI: https://doi.org/10.1115/1.4038771

Published Online: March 5, 2018

.... Editor: Leon Cizelj. 24 08 2017 26 11 2017 Nuclear engineering Reactor physics Standards Licensing Regulatory issues Codes Transport theory Burnup calculation is an important issue in reactor core calculation and analysis, and it is also the basis of fuel management...

View Article titled, Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Topics: Algorithms, Chain, Errors, Nuclides, Polynomial approximation, Physics

Journal Articles

Anticipated Operational Occurrences That Could Develop into Serious Accidents

Samuel Miranda

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020909.

Paper No: NERS-16-1129

DOI: https://doi.org/10.1115/1.4038160

Published Online: March 5, 2018

....pdf [8] U.S. NRC, 2005 , “Anticipated Transients that Could Develop into More Serious Events,” NRC Regulatory Issue Summary (RIS) 2005-29, U.S. Nuclear Regulatory Commission, Rockville, MD, Dec. 14, ADAMS No. ML051890212 ; https...

View Article titled, Anticipated Operational Occurrences That Could Develop into Serious Accidents

Topics: Accidents, Design, Emergency core cooling systems, Flow (Dynamics), Platform supply vessels, Pressure, Safety, Water, Licensing

Journal Articles

Special Section: Selected and Revised Papers From ICONE-24

Asif Arastu, Yassin Hasan, Leon Cizelj, Jovica R. Riznic, Guoqiang Wang

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020201.

Paper No: NERS-18-1006

DOI: https://doi.org/10.1115/1.4039038

Published Online: March 5, 2018

...Asif Arastu; Yassin Hasan; Leon Cizelj; Jovica R. Riznic; Guoqiang Wang 09 01 2018 16 01 2018 Advanced reactors Nuclear engineering Nuclear safety Plant systems Thermal hydraulics Standards Licensing Regulatory issues Codes Plant construction Plant components Plant...

View Article titled, Special Section: Selected and Revised Papers From ICONE-24

Topics: Licensing, Nuclear engineering, Plant construction, Safety, Security, Thermal hydraulics

Journal Articles

Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Stephen A. Hambric, Samir Ziada, Richard J. Morante

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021002.

Paper No: NERS-17-1059

DOI: https://doi.org/10.1115/1.4037898

Published Online: March 5, 2018

... details on BWR plant operation, see the U.S. Nuclear Regulatory Commission (USNRC) BWR Reactor Concepts Manual (available on the NRC public website) [ 1 ]. Nuclear safety Plant operations Standards Licensing Regulatory issues Codes Plant engineering Plant modifications Plant life cycle...

View Article titled, Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Topics: Steam, Stress, Boiling water reactors, Dryers

Journal Articles

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041009.

Paper No: NERS-17-1021

DOI: https://doi.org/10.1115/1.4037188

Published Online: July 31, 2017

.... Advanced reactors Fusion Engineering Nuclear engineering Research reactors Thermal hydraulics Standards Licensing Regulatory issues Codes Copyright © 2017 by ASME 2017 2332-8983/2017/3(4)/041009/13/ $25.00 ...

View Article titled, Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

Topics: Accidents, Coolants, Flow (Dynamics), Vessels, Temperature, Heat, Pressure, Cooling systems, Water, Tungsten

Journal Articles

Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Sri Budi Utami, Susetyo Hario Putero

ASME J of Nuclear Rad Sci. October 2017, 3(4): 044501.

Paper No: NERS-16-1102

DOI: https://doi.org/10.1115/1.4037078

Published Online: July 31, 2017

... and guidance are needed to be established by BAPETEN in order to complete the current regulations so that problems can all be anticipated. 13 09 2016 12 06 2017 Issues Standards Licensing Regulatory issues Codes Based on Indonesia Nuclear Energy Act of 1997 [ 1 ], any use...

View Article titled, Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Topics: Nuclear decommissioning, Nuclear power stations, Safety, Licensing

Journal Articles

Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020906.

Paper No: NERS-16-1120

DOI: https://doi.org/10.1115/1.4035851

Published Online: March 1, 2017

... purposes. 29 09 2016 16 12 2016 Coupled codes Nuclear safety Thermal hydraulics Standards Licensing Regulatory issues Codes Security Because the nuclear power industry continually improves its designs, safety equipment, processes, and analysis methods, the Nuclear...

View Article titled, Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

Topics: Accidents, Cladding systems (Building), Coolants, Cycles, Design, Flow (Dynamics), Fuels, Nuclear fuel cycle, Oxidation, Safety

Journal Articles

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005.

Paper No: NERS-15-1226

DOI: https://doi.org/10.1115/1.4033813

Published Online: December 20, 2016

... December 20, 2016. Assoc. Editor: Emmanuel Porcheron. 4 11 2015 26 5 2016 28 5 2016 Advanced reactors Standards Licensing Regulatory issues Codes The HTTR [ 1 ] is a block-type HTGR with the outlet gas temperature of 950°C. It is difficult to insert all of the control...

View Article titled, Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Topics: High temperature, Neutron flux, Rods, Fuels, Design, Temperature, Computational methods

Journal Articles

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011013.

Paper No: NERS-15-1220

DOI: https://doi.org/10.1115/1.4033812

Published Online: December 20, 2016

... received May 31, 2016; published online December 20, 2016. Assoc. Editor: Emmanuel Porcheron. 21 10 2015 31 5 2016 1 6 2016 Advanced reactors Research reactors Standards Licensing Regulatory issues Codes The HTTR [1] is a block-type HTGR. Since the first...

View Article titled, Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

Topics: Evaluation methods, High temperature, Temperature, Design, Cycles, Temperature distribution, Physics, Very high temperature reactors

Journal Articles

Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique

Francesco Cordella, Mauro Cappelli, Massimo Sepielli

ASME J of Nuclear Rad Sci. October 2016, 2(4): 041003.

Paper No: NERS-15-1181

DOI: https://doi.org/10.1115/1.4033696

Published Online: October 12, 2016

... Research reactors Thermal hydraulics Standards Licensing Regulatory issues Codes TDR is a well-known technique that has been applied in a wide variety of applications in different science and technology fields (for a recent comprehensive review of TDR-based monitoring solutions, see Ref. [ 1...

View Article titled, Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique

Topics: Algorithms, Boilers, Dynamics (Mechanics), Pressure, Sensors, Temperature, Transients (Dynamics), Water, Flow (Dynamics), Transmission lines

Journal citation

NARROW

Research on the Application of F en for Environmentally Assisted Fatigue Evaluation of the Austenitic SS Pipe Under Combined Transient Loads

Planning the Selection and Assignment of Security Forensics Countermeasures

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Anticipated Operational Occurrences That Could Develop into Serious Accidents

Special Section: Selected and Revised Papers From ICONE-24

Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique

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