Sensitivity Degradation Characteristics of Incore Neutron Detector for Heavy Water Reactor, Fugen NPP

2002 ◽  
Author(s):  
Tsuyoshi Okawa ◽  
Naoyuki Yomori
Keyword(s):  
Thermal Neutron ◽  
Heavy Water ◽  
Power Distribution ◽  
Neutron Detector ◽  
Nuclear Power ◽  
Operating Cost ◽  
Water Reactor ◽  
Mox Fuel ◽  
Heavy Water Reactor ◽  
Test Reactor

Fugen nuclear power plant is a 165MWe, heavy water-moderated, boiling light water-cooled, pressure tube-type reactor developed by JNC, which is the world’s first thermal neutron power reactor to utilize mainly Uranium and Plutonium mixed oxide (MOX) fuel. Fugen has been loaded a total of 726 MOX fuel assemblies since the initial core in 1978. Each incore neutron detector assembly of Fugen composed of four Local Power Monitors (LPM) is located at sixteen positions in the area of heavy water moderator in the core and monitors its power distribution during operation. The thermal neutron flux of Fugen is relatively higher than that of Boiling Water Reactor (BWR), therefore LPM, which is comprised of a fission chamber, degrades more quickly than that of BWR. An Improved Long-life LPM (LLPM) pasted inner surface wall of the chamber with 234U/235U at a ratio of 4 to 1 had been developed through the irradiation test at Japan Material Test Reactor (JMTR). The 234U is converted to 235U with absorption of neutron, and compensates the consumption of 235U. LPM has been loaded to the initial core of Fugen since 1978. JNC had evaluated its sensitivity degradation characteristics through the accumulated irradiation data and the parametric survey for 234σa and 235σa. Based on the experience of evaluation for sensitivity degradation, JNC has applied shuffling operation of LPM assemblies during an annual inspection outage to reduce the operating cost. This operation realizes the reduction of replacing number of LPM assemblies and volume of radioactive waste. This paper describes the sensitivity degradation characteristics of incore neutron detector and the degradation evaluation methods established in Fugen.

Decoupling Criteria for Multi-Connected Equipment

1998 ◽  
Vol 120 (1) ◽  
pp. 93-98 ◽  
Author(s):  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
S. C. Mahajan ◽  
K. Suzuki
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Internal Structure ◽  
Heavy Water ◽  
Nuclear Power ◽  
Seismic Analysis ◽  
Real Life ◽  
Water Reactor ◽  
Reactor Building ◽  
Heavy Water Reactor

Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water reactor building internal structure and steam generator.

scholarly journals Advanced Heavy Water Reactor: A New Step Toward Sustainability

2021 ◽  
Vol 8 (3A) ◽  
Author(s):  
Ricardo Bastos Smith ◽  
Mahima Sachdeva ◽  
Indranil Bisuri ◽  
Roberto Vicente
Keyword(s):  
United States ◽  
Green Chemistry ◽  
Heavy Water ◽  
Half Life ◽  
Nuclear Power ◽  
The United States ◽  
Water Reactor ◽  
Nuclear Field ◽  
Heavy Water Reactor ◽  
Enriched Uranium

One of the great advances in the current evolution of nuclear power reactors is occurring in India, with the Advanced Heavy Water Reactor (AHWR). It is a reactor that uses thorium as part of its fuel, which in its two fueling cycle options, in conjunction with plutonium or low enriched uranium, produces energy at the commercial level, generating less actinides of long half-life and inert thorium oxide, which leads to an optimization in the proportion of energy produced versus the production of burnt fuels of the order of up to 50%. The objective of this work is to present the most recent research and projects in progress in India, and how the expected results should be in compliance with the current sustainability models and programs, especially the "Green Chemistry", a program developed since the 1990s in the United States and England, which defines sustainable choices in its twelve principles and that can also be mostly related to the nuclear field. Nevertheless, in Brazil, for more than 40 years there has been the discontinuation of research for a thorium-fueled reactor, and so far there has been no prospect of future projects. The AHWR is an important example as an alternative way of producing energy in Brazil, as the country has the second largest reserve of thorium on the planet.

Integral Sliding Mode for Power Distribution Control of Advanced Heavy Water Reactor

2020 ◽  
Vol 67 (6) ◽  
pp. 1076-1085 ◽  
Author(s):  
R. J. Desai ◽  
B. M. Patre ◽  
R. K. Munje ◽  
A. P. Tiwari ◽  
S. R. Shimjith
Keyword(s):  
Heavy Water ◽  
Power Distribution ◽  
Sliding Mode ◽  
Water Reactor ◽  
Integral Sliding Mode ◽  
Heavy Water Reactor ◽  
Power Distribution Control

Aerial work robot for a nuclear power plant with a pressurized heavy water reactor

2016 ◽  
Vol 92 ◽  
pp. 284-288 ◽  
Author(s):  
Hocheol Shin ◽  
Changhoi Kim ◽  
Yongchil Seo ◽  
Kyungmin Jeong ◽  
Youngsoo Choi ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Heavy Water ◽  
Nuclear Power ◽  
Water Reactor ◽  
Heavy Water Reactor

A Case Study for INPRO Methodology Based on Indian Advanced Heavy Water Reactor

2004 ◽  
Author(s):  
K. Anantharaman ◽  
D. Saha ◽  
R. K. Sinha
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Energy System ◽  
Water Reactor ◽  
Fuel Cycles ◽  
Heavy Water Reactor ◽  
Tube Type ◽  
Near Future

Under Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a methodology (INPRO methodology) has been developed which can be used to evaluate a given energy system or a component of such a system on a national and/or global basis. The INPRO study can be used for assessing the potential of the innovative reactor in terms of economics, sustainability and environment, safety, waste management, proliferation resistance and cross cutting issues. India, a participant in INPRO program, is engaged in a case study applying INPRO methodology based on Advanced Heavy Water Reactor (AHWR). AHWR is a 300 MWe, boiling light water cooled, heavy water moderated and vertical pressure tube type reactor. Thorium utilization is very essential for Indian nuclear power program considering the indigenous resource availability. The AHWR is designed to produce most of its power from thorium, aided by a small input of plutonium-based fuel. The features of AHWR are described in the paper. The case study covers the fuel cycle, to be followed in the near future, for AHWR. The paper deals with initial observations of the case study with regard to fuel cycle issues.

Non-Linear Analysis of Out-of-Phase Instabilities in Advanced Heavy Water Reactor

2007 ◽  
Author(s):  
S. S. Bahga ◽  
J. B. Doshi
Keyword(s):  
Boundary Conditions ◽  
Heavy Water ◽  
Power Distribution ◽  
Transfer Model ◽  
Two Phase ◽  
Thermally Induced ◽  
Water Reactor ◽  
One Dimensional ◽  
Heavy Water Reactor ◽  
Phase Instabilities

In this paper we study thermally induced instabilities in Indian Advanced Heavy Water Reactor (AHWR). One dimensional homogeneous equilibrium model has been used to simulate the two-phase flow. The nonlinear mass, momentum and energy conservation equations are solved along the characteristic directions by using implicit finite difference scheme. The virtue of this scheme is that it handles the boundary conditions naturally. This scheme is fast because the time steps can be greater than that given by Courant-Friedrichs-Lewy condition. The numerical scheme is sufficiently general and can handle axially varying heat flux and different combinations of inlet and exit boundary conditions of enthalpy, mass flux and pressure and multiple channels. No assumptions regarding constant properties and in-compressibility have been taken. The one dimensional fuel heat transfer model was then coupled to the thermal-hydraulics model to analyze out-of-phase instabilities in AHWR. Out-of-phase oscillations are studied by considering two parallel boiling channels. Further effects of radial power distribution, inlet orificing and axial power distribution were considered.

Operating Experience with MOX Fuel Loaded Heavy Water Reactor

1993 ◽  
Vol 30 (1) ◽  
pp. 78-88 ◽  
Author(s):  
Yoshitake SHIRATORI ◽  
Toshiyuki FURUBAYASHI ◽  
Mitsuo MATSUMOTO
Keyword(s):  
Heavy Water ◽  
Operating Experience ◽  
Water Reactor ◽  
Mox Fuel ◽  
Heavy Water Reactor

Pressurized Heavy Water Reactor Technology: Its Relevance Today

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
A. K. Nayak ◽  
S. Banerjee
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
Substantial Improvement ◽  
Natural Uranium ◽  
Excellent Performance ◽  
Water Reactor ◽  
Reactor Technology ◽  
Mox Fuel ◽  
Heavy Water Reactor ◽  
Water Reactors

The pressurized heavy water reactor (PHWR) technology was conceived in Canada and has moved to several nations for commercial production of electricity. Currently, 49 power reactors operate with PHWR technology producing nearly 25 GWe. The technology is flexible for adopting different fuel cycle options which include natural uranium, different mixed oxide (MOX) fuel, and thorium. The technology has made substantial improvement in materials, construction, and safety since its inception. PHWRs have demonstrated excellent performance historically. Their safety statistics are excellent. Indian PHWRs also have shown economic competitiveness even in small sizes, thus providing an ideal design for new entrants. While the technology features of PHWRs are available even in textbooks, the objective of this paper is to highlight the historical development and salient features, and innovations for further improvement in operation, safety and economics. Thus, this paper shall serve as a curtain raiser for the special issue “Pressurized Heavy Water Reactors (PHWRs) Safety: Post Fukushima.”

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