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RSS2017 Vol. 29, No. 03
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2017,
29: 036001.
doi: 10.11884/HPLPB201729.160297
Abstract:
Transient calculation is one of the key parts in reactor safety analysis and system simulation. With the fast development of computer technology, now 3D spatial dependent kinetics calculation is feasible and has already been used in the system simula...
Transient calculation is one of the key parts in reactor safety analysis and system simulation. With the fast development of computer technology, now 3D spatial dependent kinetics calculation is feasible and has already been used in the system simula...
2017,
29: 036002.
doi: 10.11884/HPLPB201729.160302
Abstract:
The depletion calculation in reactor physics requires depletion chain data. However, the depletion chain that originates from evaluated nuclear data library is unnecessarily detailed for assembly and micro-depletion calculation, while conventional de...
The depletion calculation in reactor physics requires depletion chain data. However, the depletion chain that originates from evaluated nuclear data library is unnecessarily detailed for assembly and micro-depletion calculation, while conventional de...
2017,
29: 036003.
doi: 10.11884/HPLPB201729.160286
Abstract:
BEAVRS is an international benchmark model based on the commercial PWR reactor with full-core meticulous modeling from MIT, and it has detailed measurement data. BEAVRS is a large 3D reactor benchmark for verification consisted of a variety of enrich...
BEAVRS is an international benchmark model based on the commercial PWR reactor with full-core meticulous modeling from MIT, and it has detailed measurement data. BEAVRS is a large 3D reactor benchmark for verification consisted of a variety of enrich...
2017,
29: 036004.
doi: 10.11884/HPLPB201729.160433
Abstract:
Nuclear power software needs to give the uncertainty of calculation results, thus it can effectively evaluate the safety of nuclear power. Nuclear data are important sources of uncertainty in core calculation, and the sensitivity analysis is an impor...
Nuclear power software needs to give the uncertainty of calculation results, thus it can effectively evaluate the safety of nuclear power. Nuclear data are important sources of uncertainty in core calculation, and the sensitivity analysis is an impor...
2017,
29: 036005.
doi: 10.11884/HPLPB201729.160339
Abstract:
The traveling wave reactor (TWR) is an innovative nuclear system, whose discharge burnup is 400 GWd/tHM, about three to four times of existing fast reactor and six to eight times of pressurized water reactor. High discharge burnup forces the present ...
The traveling wave reactor (TWR) is an innovative nuclear system, whose discharge burnup is 400 GWd/tHM, about three to four times of existing fast reactor and six to eight times of pressurized water reactor. High discharge burnup forces the present ...
2017,
29: 036006.
doi: 10.11884/HPLPB201729.160357
Abstract:
Large equipment models need tremendous amount of three-dimensional solid entities to build, when using CSG method. For example, Dayawan reactor whole core model has tens of thousands of solid entities. A large-scale visual modeling software JLAMT for...
Large equipment models need tremendous amount of three-dimensional solid entities to build, when using CSG method. For example, Dayawan reactor whole core model has tens of thousands of solid entities. A large-scale visual modeling software JLAMT for...
2017,
29: 036007.
doi: 10.11884/HPLPB201729.160383
Abstract:
Coupled neutronics and thermal-hydraulics calculation can enhance the computational accuracy in reactor simulation. With the development of computational capability, the coupled Monte-Carlo neutron transportation and thermal-hydraulics calculation pl...
Coupled neutronics and thermal-hydraulics calculation can enhance the computational accuracy in reactor simulation. With the development of computational capability, the coupled Monte-Carlo neutron transportation and thermal-hydraulics calculation pl...
2017,
29: 036008.
doi: 10.11884/HPLPB201729.160179
Abstract:
The reactor pressure vessel (RPV) neutron flux calculation method for MOX fuel core was preliminarily researched, especially the core source calculation method for MOX fuel core. Based on three-dimensional discrete ordinate code TORT, the RPV fast ne...
The reactor pressure vessel (RPV) neutron flux calculation method for MOX fuel core was preliminarily researched, especially the core source calculation method for MOX fuel core. Based on three-dimensional discrete ordinate code TORT, the RPV fast ne...
2017,
29: 036009.
doi: 10.11884/HPLPB201729.160294
Abstract:
Zero power physics test (ZPPT) is implanted after the nuclear reactor approach to criticality to make sure the core performance is in compliance with the nuclear design. However, traditional equipment used in ZPPT is bulk in volume and the measuremen...
Zero power physics test (ZPPT) is implanted after the nuclear reactor approach to criticality to make sure the core performance is in compliance with the nuclear design. However, traditional equipment used in ZPPT is bulk in volume and the measuremen...
2017,
29: 036010.
doi: 10.11884/HPLPB201729.160376
Abstract:
Fuel loading pattern optimization with MOX (mixed oxide of plutonium and uranium) fuel is an important aspect for GIII LWR. For the HPR1000 core, an optimized MOX fuel is designed. Based on which, two loading patterns with 50% MOX fuel are designed. ...
Fuel loading pattern optimization with MOX (mixed oxide of plutonium and uranium) fuel is an important aspect for GIII LWR. For the HPR1000 core, an optimized MOX fuel is designed. Based on which, two loading patterns with 50% MOX fuel are designed. ...
2017,
29: 036011.
doi: 10.11884/HPLPB201729.160172
Abstract:
Power control banks-turbine load test (RGL04 test) is to be performed to verify the accuracy of calibration curve by quickly reducing the power before nuclear power plants connecting to power grid. Overheating phenomenon occurred during the tests in ...
Power control banks-turbine load test (RGL04 test) is to be performed to verify the accuracy of calibration curve by quickly reducing the power before nuclear power plants connecting to power grid. Overheating phenomenon occurred during the tests in ...
2017,
29: 036012.
doi: 10.11884/HPLPB201729.160338
Abstract:
In the field of nuclear arms control, non-proliferation is an significant area, particularly the proliferation of weapon usable nuclear materials, which is concerned by many countries. We used burnup calculating code MCORGS to simulate the relation b...
In the field of nuclear arms control, non-proliferation is an significant area, particularly the proliferation of weapon usable nuclear materials, which is concerned by many countries. We used burnup calculating code MCORGS to simulate the relation b...
2017,
29: 036013.
doi: 10.11884/HPLPB201729.160191
Abstract:
Ex-core detector response function represents the contribution to the detector tally from each reactor core assembly, reflects the relationship between reactor core power distribution and detector tally. In this paper, the adjoint transport calculati...
Ex-core detector response function represents the contribution to the detector tally from each reactor core assembly, reflects the relationship between reactor core power distribution and detector tally. In this paper, the adjoint transport calculati...
2017,
29: 036014.
doi: 10.11884/HPLPB201729.160298
Abstract:
The fast, accurate and highly automatic power regulation ability in a large range is a main research objective of advanced nuclear power plant control strategy. In the current PWR plant, the mechanical shim control and operation strategy is a good me...
The fast, accurate and highly automatic power regulation ability in a large range is a main research objective of advanced nuclear power plant control strategy. In the current PWR plant, the mechanical shim control and operation strategy is a good me...
2017,
29: 036015.
doi: 10.11884/HPLPB201729.160189
Abstract:
Nuclear criticality safety is one of the most important security issues in the process of development of nuclear industry, in which evaluation and analysis of critical accidents is the foundation of shielding design and emergency plan after critical ...
Nuclear criticality safety is one of the most important security issues in the process of development of nuclear industry, in which evaluation and analysis of critical accidents is the foundation of shielding design and emergency plan after critical ...
2017,
29: 036016.
doi: 10.11884/HPLPB201729.160355
Abstract:
With the development of nuclear power industry, spent fuel of nuclear power plant is increasing. The disposal of minor actinides(MA) of spent nuclear fuel in nuclear power plants is not only an important process of recycling nuclear fuel, but also ke...
With the development of nuclear power industry, spent fuel of nuclear power plant is increasing. The disposal of minor actinides(MA) of spent nuclear fuel in nuclear power plants is not only an important process of recycling nuclear fuel, but also ke...
2017,
29: 036017.
doi: 10.11884/HPLPB201628.160291
Abstract:
The 3-D Monte Carlo transport code JMCT is developed by Software Center for High Performance Numerical Simulation independently and JLAMT is its pre-processing visualized modeling tool. Benchmarks including BW, KRITZ, BEAVRS et al were simulated by J...
The 3-D Monte Carlo transport code JMCT is developed by Software Center for High Performance Numerical Simulation independently and JLAMT is its pre-processing visualized modeling tool. Benchmarks including BW, KRITZ, BEAVRS et al were simulated by J...
2017,
29: 036018.
doi: 10.11884/HPLPB201729.160194
Abstract:
Nuclear reactors will produce a large number of neutrons when the plant is in operation. The neutrons could have strong effect on in-core materials and generate active products which could cause destructive effects on staff. Therefore, the high preci...
Nuclear reactors will produce a large number of neutrons when the plant is in operation. The neutrons could have strong effect on in-core materials and generate active products which could cause destructive effects on staff. Therefore, the high preci...
2017,
29: 036019.
doi: 10.11884/HPLPB201729.160399
Abstract:
In order to compare core characteristics of conventional fast reactor with travelling wave reactor, a conceptual neutronic design of conventional fast reactor called HBFR (High Burnup Fast Reactor) with maximum burnup up to 300 000 MWd/tHM was given....
In order to compare core characteristics of conventional fast reactor with travelling wave reactor, a conceptual neutronic design of conventional fast reactor called HBFR (High Burnup Fast Reactor) with maximum burnup up to 300 000 MWd/tHM was given....
2017,
29: 036020.
doi: 10.11884/HPLPB201729.160400
Abstract:
Reactor shielding calculations is the foundation for assessing nuclear plant safety performance. It is also an important method to provide guidelines for constructions and operations of nuclear plant. JSNT is a massively parallel discrete ordinates t...
Reactor shielding calculations is the foundation for assessing nuclear plant safety performance. It is also an important method to provide guidelines for constructions and operations of nuclear plant. JSNT is a massively parallel discrete ordinates t...
2017,
29: 036021.
doi: 10.11884/HPLPB201729.160326
Abstract:
The incident energy of thermal neutron ranges from 110-5 eV to 5 eV, which is comparable to energy of thermal motion of nuclide in the reactor, the reactions between neutron and target have vastly different characteristic in this energy range. The co...
The incident energy of thermal neutron ranges from 110-5 eV to 5 eV, which is comparable to energy of thermal motion of nuclide in the reactor, the reactions between neutron and target have vastly different characteristic in this energy range. The co...
2017,
29: 036022.
doi: 10.11884/HPLPB201729.160192
Abstract:
KYCORE is a radial MOC and axial SN coupled neutron transport software developed by China Institute of Nuclear Power. Its highly accurate coupling between 2D MOC and 1D SN is realized by angular flux, which is one of the most accurate methods applyin...
KYCORE is a radial MOC and axial SN coupled neutron transport software developed by China Institute of Nuclear Power. Its highly accurate coupling between 2D MOC and 1D SN is realized by angular flux, which is one of the most accurate methods applyin...
2017,
29: 036023.
doi: 10.11884/HPLPB201729.160186
Abstract:
This paper studies and proposes a mechanism-based calculation method of secondary neutron source (SNS) intensity of nuclear reactor, and calculated the SNS intensity of the reactor of a certain nuclear power plant at the refueling outage of the secon...
This paper studies and proposes a mechanism-based calculation method of secondary neutron source (SNS) intensity of nuclear reactor, and calculated the SNS intensity of the reactor of a certain nuclear power plant at the refueling outage of the secon...
2017,
29: 036024.
doi: 10.11884/HPLPB201729.160333
Abstract:
This paper studies the application of solving high temperature reactor (HTR) neutron diffusion equation with Jacobian-free Newton-Krylov (JFNK) method. Results show that when solving neutron diffusion equation, the relative residual norm of JFNK meth...
This paper studies the application of solving high temperature reactor (HTR) neutron diffusion equation with Jacobian-free Newton-Krylov (JFNK) method. Results show that when solving neutron diffusion equation, the relative residual norm of JFNK meth...
2017,
29: 036025.
doi: 10.11884/HPLPB201729.160424
Abstract:
The burnup calculation of reactors is related to the fuel management of the reactor, and directly affect the economic evaluation of the core, therefore how to calculate burnup characteristics of reactors faster and better is an important part of the ...
The burnup calculation of reactors is related to the fuel management of the reactor, and directly affect the economic evaluation of the core, therefore how to calculate burnup characteristics of reactors faster and better is an important part of the ...
