Monte Carlo boundary source approach in MOX fuel test capsule design

Chang, G S; Ryskamp, J M

Title: Monte Carlo boundary source approach in MOX fuel test capsule design

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Abstract

To demonstrate that the differences between weapons-grade (WG) mixed oxide (MOX) and reactor-grade MOX fuel are minimal, and therefore the commercial MOX experience base is applicable, an average power test (6 to 10 kW/ft) of WG MOX fuel was inserted into the Advanced Test Reactor (ATR) in January 1998. A high-power test (10 to 15 kW/ft) of WG MOX fuel in ATR is being fabricated as a follow-on to the average-power test. Two MOX capsules with 8.9 GWd/t burnup were removed from ATR on September 13, 1998, and replaced by two fresh WG MOX fuel capsules in regions with less thermal neutron flux (top-1 and bottom-1, which are away from the core center). To compensate for {sup 239}Pu depletion, which causes the linear heat generation rates (LHGRs) to decrease, the INCONEL shield was replaced by an aluminum shield in the phase-II irradiation. The authors describe and compare the results of the detailed MCNP ATR quarter core model (QCM) and isolated box model with boundary source (IBMBS). Physics analysis were performed with these two different models to provide the neutron/fission heat rate distribution data in the WG MOX fuel test assembly, with INCONEL and aluminum shrouds, located in the small I-24more » hole of ATR.« less

Authors:

Chang, G S; Ryskamp, J M ^[1]

Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)

Publication Date:: Wed Sep 01 00:00:00 EDT 1999

OSTI Identifier:: 678163

Report Number(s):: CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009148

Resource Type:: Journal Article

Journal Name:: Transactions of the American Nuclear Society

Additional Journal Information:: Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999

Country of Publication:: United States

Language:: English

Subject:: 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; MIXED OXIDE FUELS; ATR REACTOR; NUCLEAR WEAPONS DISMANTLEMENT; PLUTONIUM OXIDES; BURNUP; MONTE CARLO METHOD; PERFORMANCE TESTING

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                    Chang, G S, and Ryskamp, J M. Monte Carlo boundary source approach in MOX fuel test capsule design.  United States: N. p., 1999. 
        Web.

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                    Chang, G S, & Ryskamp, J M. Monte Carlo boundary source approach in MOX fuel test capsule design.  United States.

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                    Chang, G S, and Ryskamp, J M. 1999.  
        "Monte Carlo boundary source approach in MOX fuel test capsule design".  United States.

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@article{osti_678163,

  title        = {Monte Carlo boundary source approach in MOX fuel test capsule design},

  author       = {Chang, G S and Ryskamp, J M},

  abstractNote = {To demonstrate that the differences between weapons-grade (WG) mixed oxide (MOX) and reactor-grade MOX fuel are minimal, and therefore the commercial MOX experience base is applicable, an average power test (6 to 10 kW/ft) of WG MOX fuel was inserted into the Advanced Test Reactor (ATR) in January 1998. A high-power test (10 to 15 kW/ft) of WG MOX fuel in ATR is being fabricated as a follow-on to the average-power test. Two MOX capsules with 8.9 GWd/t burnup were removed from ATR on September 13, 1998, and replaced by two fresh WG MOX fuel capsules in regions with less thermal neutron flux (top-1 and bottom-1, which are away from the core center). To compensate for {sup 239}Pu depletion, which causes the linear heat generation rates (LHGRs) to decrease, the INCONEL shield was replaced by an aluminum shield in the phase-II irradiation. The authors describe and compare the results of the detailed MCNP ATR quarter core model (QCM) and isolated box model with boundary source (IBMBS). Physics analysis were performed with these two different models to provide the neutron/fission heat rate distribution data in the WG MOX fuel test assembly, with INCONEL and aluminum shrouds, located in the small I-24 hole of ATR.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/678163},
  journal      = {Transactions of the American Nuclear Society},
number       = ,

  volume       = 80,

  place        = {United States},

  year         = {Wed Sep 01 00:00:00 EDT 1999},

  month        = {Wed Sep 01 00:00:00 EDT 1999}

}

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